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SEC Petition Evaluation Report

Petition SEC-00196

Report Rev #: 0 Report Submittal Date: January 5, 2012______

Subject Expert(s): Jason Davis, Ray Clark

Site Expert(s): N/A

Petitioner Administrative Summary

Petition Under Evaluation

Petition #

Petition 

Type

Petition A

Receipt Date DOE/AWE Facility Name

SEC-00196 83.14 November 3, 2011 Brookhaven National Laboratory

NIOSH-Proposed Class Definition

All employees of the Department of Energy, its predecessor agencies, and its contractors and subcontractors 

who worked in any area at Brookhaven National Laboratory in Upton, New York, from January 1, 1980 

through December 31, 1993, for a number of work days aggregating at least 250 work days, occurring either 

solely under this employment, or in combination with work days within the parameters established for one or 

more other classes of employees in the Special Exposure Cohort.

Related Petition Summary Information

SEC Petition Tracking #(s) Petition Type DOE/AWE Facility Name Petition Status

SEC-00113 83.13 Brookhaven National 

Laboratory

Class added to the SEC: 

January 1, 1947 through

December 31, 1979

Related Evaluation Report Information

Report Title DOE/AWE Facility Name

SEC Petition Evaluation Report for Petition SEC-00113 Brookhaven National Laboratory

ORAU Lead Technical Evaluator: Jason Davis ORAU Peer Review Completed By: Daniel Stempfley

[Signature on File]

 

Peer Review Completed By: 01/06/2012

Grady Calhoun Date

SEC Petition Evaluation Reviewed By: [Signature on File] 01/06/2012

J. W. Neton Date

SEC Evaluation Approved By: [Signature on File] 01/06/2012

Stuart L. Hinnefeld Date
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Evaluation Report Summary: SEC-00196, 

Brookhaven National Laboratory

This evaluation report by the National Institute for Occupational Safety and Health (NIOSH) addresses a 

class of employees proposed for addition to the Special Exposure Cohort (SEC) per the Energy 

Employees Occupational Illness Compensation Program Act of 2000, as amended, 42 U.S.C. § 7384 et 

seq. (EEOICPA) and 42 C.F.R. pt. 83, Procedures for Designating Classes of Employees as Members of 

the Special Exposure Cohort Under the Energy Employees Occupational Illness Compensation Program 

Act of 2000.

NIOSH-Proposed Class Definition

All employees of the Department of Energy, its predecessor agencies, and its contractors and 

subcontractors who worked in any area at Brookhaven National Laboratory in Upton, New York, from 

January 1, 1980 through December 31, 1993, for a number of work days aggregating at least 250 work 

days, occurring either solely under this employment, or in combination with work days within the 

parameters established for one or more other classes of employees in the Special Exposure Cohort.

Feasibility of Dose Reconstruction Findings

NIOSH lacks sufficient information, which includes in vivo and in-vitro monitoring data, to allow it to 

estimate with sufficient accuracy the potential internal exposures to various radionuclides to which the 

proposed class may have been subjected. NIOSH finds that it is likely feasible to reconstruct 

occupational medical dose for Brookhaven National Laboratory workers with sufficient accuracy.

The NIOSH dose reconstruction feasibility findings are based on the following:

Principal sources of internal and external radiation for members of the proposed class included 

exposures to plutonium, uranium, tritium, fission and activation products, transuranic radionuclides, 

nuclear reactors, linear accelerators, radiography equipment, and a wide variety of other radioactive 

materials. 

NIOSH previously determined in its evaluation of petition SEC-00113 that it did not have access to 

sufficient urinalysis, air sampling data, in vivo, or in vitro analyses records to estimate internal 

exposures for the period evaluated (NIOSH, 2009). In 2010, DHHS designated the following class 

for inclusion in the SEC:

All employees of the Department of Energy, its predecessor agencies, and its contractors and 

subcontractors who worked at Brookhaven National Laboratory in Upton, New York, from January 1, 

1947 to December 31, 1979, for a number of work days aggregating at least 250 work days, 

occurring either solely under this employment, or in combination with work days within the 

parameters established for one or more other classes of employees in the Special Exposure Cohort 

(DHHS, 2010).
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NIOSH has determined that, due to undocumented worker movements across the site and limited 

claimant-specific information pertaining to work locations, it is unable to eliminate any specific 

worker from potential exposure scenarios based on assigned work location. NIOSH has found that a 

determination cannot always be made as to whether or not an employee worked in technical areas 

with a history of radioactive material use, or whether an employee should have been monitored for 

radiological exposures. 

Through the course of on-going dose reconstruction and research associated with the SEC-00113 

class period, NIOSH has determined that, due to on-going difficulty of consistently obtaining all 

requested personnel monitoring records for individual BNL claims, NIOSH is unable to estimate with 

sufficient accuracy internal exposures for workers at Brookhaven National Laboratory during the time

period from January 1, 1980 through December 31, 1993. 

NIOSH found that external exposure, including occupational medical doses, could be reconstructed 

for all employees between January 1, 1980 and December 31, 1993, consistent with the determination 

in the evaluation of SEC-00113 (NIOSH, 2009).

Pursuant to 42 C.F.R. § 83.13(c)(1), NIOSH determined that there is insufficient information to 

either: (1) estimate the maximum radiation dose, for every type of cancer for which radiation doses 

are reconstructed, that could have been incurred under plausible circumstances by any member of the 

class; or (2) estimate the radiation doses of members of the class more precisely than a maximum 

dose estimate.

Although NIOSH found that it is not possible to completely reconstruct radiation doses for the proposed 

class, NIOSH intends to use any internal and external monitoring data that may become available for an 

individual claim (and that can be interpreted using existing NIOSH dose reconstruction processes or 

procedures). Therefore, dose reconstructions for individuals employed in any area at Brookhaven 

National Laboratory during the period from January 1, 1980 through December 31, 1993, but who do not 

qualify for inclusion in the SEC, may be performed using these data as appropriate.

Health Endangerment Determination

The NIOSH evaluation did not identify any evidence supplied by the petitioners or from other resources 

that would establish that the class was exposed to radiation during a discrete incident likely to have 

involved exceptionally high-level exposures, such as nuclear criticality incidents or other events involving 

similarly high levels of exposures. However, the evidence reviewed in this evaluation indicates that some 

workers in the class may have accumulated chronic radiation exposures through intakes of various 

radionuclides and from direct exposure to radioactive materials or radiation-producing equipment. 

Therefore, 42 C.F.R. § 83.13(c)(3)(ii) requires NIOSH to specify that health may have been endangered 

for those workers covered by this evaluation who were employed for a number of work days aggregating 

at least 250 work days within the parameters established for this class or in combination with work days 

within the parameters established for one or more other classes of employees in the SEC.
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Table of Contents

Evaluation Report Summary: SEC-00196, Brookhaven National Laboratory............................... 3

1.0 Purpose and Scope .............................................................................................................. 7

2.0 Introduction......................................................................................................................... 7

3.0 NIOSH-Proposed Class Definition and Petition Basis....................................................... 8

4.0 Radiological Operations Relevant to the Proposed Class................................................... 9

4.1 Operations Description ...............................................................................................9

4.2 Radiation Exposure Potential from Operations ........................................................13

4.2.1 Photon ...........................................................................................................13

4.2.2 Beta ...............................................................................................................13

4.2.3 Neutron .........................................................................................................14

4.2.4 Radioactive Source Materials.......................................................................14

4.2.4.1 Uranium ........................................................................................ 15

4.2.4.2 Fission and Activation Products ................................................... 16

4.2.4.3 Tritium .......................................................................................... 17

4.2.4.4 Thorium......................................................................................... 18

4.2.4.5 Plutonium...................................................................................... 19

4.2.4.6 Americium .................................................................................... 20

4.2.4.7 Polonium....................................................................................... 20

4.3 Time Period Associated with Radiological Operations............................................21

4.4 Site Locations Associated with Radiological Operations.........................................21

4.5 Job Descriptions Affected by Radiological Operations............................................22

5.0 Summary of Available Monitoring Data for the Proposed Class..................................... 23

5.1 Data Capture Efforts and Sources Reviewed............................................................24

5.2 Worker Interviews ....................................................................................................24

5.3 Internal Personnel Monitoring Data..........................................................................25

5.4 External Personnel Monitoring Data ........................................................................29

5.5 Workplace Monitoring Data .....................................................................................33

5.6 Radiological Source Term Data................................................................................34

6.0 Feasibility of Dose Reconstruction for the Proposed Class.............................................. 34

6.1 Feasibility of Estimating Internal Exposures............................................................35

6.2 Feasibility of Estimating External Exposures...........................................................37

6.3 Class Parameters Associated with Infeasibility ........................................................37

7.0 Summary of Feasibility Findings for Petition SEC-00196............................................... 38

8.0 Evaluation of Health Endangerment for Petition SEC-00196 .......................................... 39
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9.0 NIOSH-Proposed Class for Petition SEC-00196.............................................................. 39

10.0 Evaluation of Second Similar Class.................................................................................. 40

11.0 References......................................................................................................................... 41

Attachment 1: Data Capture Synopsis.......................................................................................... 49

Figures

Figure 4-1: Aerial view of Brookhaven National Laboratory. ..................................................... 10

Figure 5-1: Maximum External Dose Range and Average Dose by Year.................................... 32

Tables

Table 4-1: Potential Contributors to BNL Internal Dose and Their Primary Modes of Decay.... 15

Table 5-1: Internal Dosimetry Timelines and Data Source Descriptions..................................... 26

Table 5-2: Minimum Detectable Levels for Photon, Beta, and Neutron Dose............................. 29

Table 5-3: External Dosimetry Timelines and Data Source Descriptions.................................... 30
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SEC Petition Evaluation Report for SEC-00196

ATTRIBUTION AND ANNOTATION: This is a single-author document. All conclusions drawn 

from the data presented in this evaluation were made by the ORAU Team Lead Technical 

Evaluator: Jason Davis; Oak Ridge Associated Universities. The rationales for all conclusions 

in this document are explained in the associated text.

1.0 Purpose and Scope

This report evaluates the feasibility of reconstructing doses for employees who worked at a 

specific facility during a specified time. It provides information and analysis germane to 

considering a petition for adding a class of employees to the Congressionally-created SEC.

This report does not make any determinations concerning the feasibility of dose reconstruction 

that necessarily apply to any individual energy employee who might require a dose 

reconstruction from NIOSH, with the exception of the employee whose dose reconstruction 

could not be completed, and whose claim consequently led to this petition evaluation. The 

finding in this report is not the final determination as to whether or not the proposed class will be 

added to the SEC. This report will be considered by the Advisory Board on Radiation and 

Worker Health (the Board) and by the Secretary of Health and Human Services (HHS). The 

Secretary of HHS will make final decisions concerning whether or not to add one or more classes 

to the SEC in response to the petition addressed by this report.

This evaluation, in which NIOSH provides its findings both on the feasibility of estimating 

radiation doses of members of this class with sufficient accuracy and on health endangerment,

was conducted in accordance with the requirements of EEOICPA and 42 C.F.R. § 83.14.

2.0 Introduction

Both EEOICPA and 42 C.F.R. pt. 83 require NIOSH to evaluate qualified petitions requesting 

that the Department of Health and Human Services add a class of employees to the SEC. The 

evaluation is intended to provide a fair, science-based determination of whether it is feasible to 

estimate, with sufficient accuracy, the radiation doses of the proposed class of employees 

through NIOSH dose reconstructions.

1

NIOSH is required to document its evaluation in a report, and to do so, relies upon both its own 

dose reconstruction expertise as well as technical support from its contractor, Oak Ridge 

Associated Universities (ORAU). Once completed, NIOSH provides the report to both the 

petitioners and the Advisory Board on Radiation and Worker Health. The Board will consider 

the NIOSH evaluation report, together with the petition, comments of the petitioner(s) and such 

other information as the Board considers appropriate, to make recommendations to the Secretary 

 

1 NIOSH dose reconstructions under EEOICPA are performed using the methods promulgated under 42 C.F.R. pt. 

82 and the detailed implementation guidelines available at http://www.cdc.gov/niosh/ocas.
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of HHS on whether or not to add one or more classes of employees to the SEC. Once NIOSH 

has received and considered the advice of the Board, the Director of NIOSH will propose a 

decision on behalf of HHS. The Secretary of HHS will make the final decision, taking into 

account the NIOSH evaluation, the advice of the Board, and the proposed decision issued by 

NIOSH. As part of this final decision process, the petitioner(s) may seek a review of certain

types of final decisions issued by the Secretary of HHS.

2

3.0 NIOSH-Proposed Class Definition and Petition Basis

The NIOSH-proposed class includes all employees of the Department of Energy, its predecessor 

agencies, and its contractors and subcontractors who worked in any area at Brookhaven National 

Laboratory in Upton, New York, from January 1, 1980 through December 31, 1993, for a 

number of work days aggregating at least 250 work days, occurring either solely under this 

employment, or in combination with work days within the parameters established for one or 

more other classes of employees in the Special Exposure Cohort. During this period, employees 

at this facility were involved in a wide variety of scientific programs, including research and 

development in:

the fundamental structure and properties of matter.

the interactions of radiation, particles and atoms with other atoms and molecules.

the physical, chemical, and biological effects of radiation and of other energy-related 

environmental pollutants.

the production of special radionuclides and their medical applications.

energy- and nuclear-related technology.

the assessment of energy sources, transmission, and uses, including their environmental and 

health effects.

The evaluation responds to Petition SEC-00196 which was submitted by an EEOICPA claimant 

whose dose reconstruction could not be completed by NIOSH due to a lack of sufficient 

dosimetry-related information. NIOSH’s determination that it is unable to complete a dose 

reconstruction for an EEOICPA claimant is a qualified basis for submitting an SEC petition 

pursuant to 42 C.F.R. § 83.9(b).

 

2

See 42 C.F.R. pt. 83 for a full description of the procedures summarized here. Additional internal procedures are 

available at http://www.cdc.gov/niosh/ocas.
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4.0 Radiological Operations Relevant to the Proposed Class 

The following subsections summarize the radiological operations at the Brookhaven National 

Laboratory from January 1, 1980 through December 31, 1993 and the information available to 

NIOSH to characterize particular processes and radioactive source materials. Using available 

sources, NIOSH has attempted to gather process and source descriptions, information regarding 

the identity and quantities of radionuclides of concern, and information describing processes 

through which the radiation exposures of concern may have occurred and the physical 

environment in which they may have occurred. The information included within this evaluation 

report is meant only to be a summary of the available information.

4.1 Operations Description

Brookhaven National Laboratory is located in Upton, New York on a 5,265 acre site. Most of its 

main facilities comprise an area of approximately 900 acres near the center of the site (see Figure 

4-1). Outlying facilities cover about 550 acres and include the hazardous waste management 

facility (HWMF), agricultural research fields, landfill areas, and a sewage treatment plant. For 

the period evaluated by NIOSH, the Brookhaven National Laboratory workforce consisted of 

approximately 3480 workers at the end of 1993.

BNL’s early research focused on advanced physics, but expanded into its current suite of 

research in the fields of medicine, biology, chemistry, physics, materials science, nuclear 

engineering, and environmental research. BNL was organized into departments that provided 

research nuclear reactors, particle accelerators, and engineering facilities in support of the 

Biology, Chemistry, Physics, Medical, Applied Science, Accelerator, and Applied Mathematics 

Departments (ORAUT-TKBS-0048). BNL activities have been well-documented over the years 

and detailed descriptions are generally available in the public domain. Due to the large amount 

of information available for the time period under evaluation, only brief summaries of the 

available information are provided within this report. The following descriptive subsections are 

drawn from the Summary Site Profile Document for the Brookhaven National Laboratory, 

ORAUT-TKBS-0048.
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Source: NIOSH, 2009

Figure 4-1: Aerial View of Brookhaven National Laboratory.

Research Reactors

BNL’s reactor operations began in 1950 with the Brookhaven Graphite Research Reactor 

(BGRR), a research reactor used for peaceful scientific exploration in the fields of medicine, 

biology, chemistry, physics, and nuclear engineering. The BGRR operated until 1968. In 1965, 

its capacity was surpassed by the High Flux Beam Reactor (HFBR). The higher thermal neutron 

fluence of the HFBR permitted shorter irradiation times and expanded support for researchers of 

all disciplines, from solid state physics to art history. The HFBR ceased operations in December 

1996.
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Medical Research Center 

Medical research at BNL began in 1950 with the opening of one of the first hospitals devoted to

nuclear medicine. It was followed by the Medical Research Center (MRC) in 1958 and the 

Brookhaven Medical Research Reactor (BMRR) in 1959. The first nuclear reactor built 

exclusively for medical and biological research, the BMRR came on line on March 15, 1959 and 

operated until October 2000.

The Radiation Therapy Facility (RTF)

The Radiation Therapy Facility (RTF) is operated jointly by the BNL Medical Department and 

the State University of New York at Stony Brook. The RTF is a high-energy dual X-ray mode 

linear accelerator (LINAC) used for the radiation therapy of cancer patients. This accelerator 

was designed to deliver therapeutic beams of X-rays and electrons for conventional and 

advanced radiotherapy techniques. This facility began providing therapy in 1991 and is currently 

operational.

Particle Accelerators

High-energy particle physics research began in 1952 with the Cosmotron, the first particle 

physics accelerator to achieve billion-electron-volt energies. The Cosmotron operated from 1953 

to 1966. In 1960, the Alternating Gradient Synchrotron (AGS), a large accelerator, was built to 

surpass the Cosmotron’s capabilities. The AGS is capable of accelerating protons to energies up 

to 30 GeV and heavy ion beams to 15 GeV/amu. The AGS achieved full energy in 1960 and is 

still in use. 

Between 1967 and 1970, the Tandem Van de Graaff, 60-inch Cyclotron, and Vertical 

Accelerator were used for medium-energy physics investigations and for special isotope 

production. The heavy ions from the Tandem Van de Graaff can also be injected into the AGS 

for physics experiments. The Tandem Van de Graaff began operating in 1970 and continues to 

the present.

The Heavy Ion Transfer tunnel connects the coupled Tandem Van de Graaff and the AGS. The 

interconnection of these two facilities permits intermediate mass ions to be injected into the AGS 

where they can be accelerated to an energy of 15 GeV/amu. These ions then are extracted and 

sent to the AGS experimental area for physics research. The AGS Booster is a circular 

accelerator with a circumference of 200 meters that receives either a proton beam from LINAC 

or heavy ions from the Tandem Van de Graaff. The Booster accelerates proton particles and 

heavy ions before injecting them into the AGS ring. The Booster receives protons and heavy 

ions from the LINAC and Tandem Van de Graaff facilities to increase their intensity for delivery 

to the AGS.

The Brookhaven LINAC Isotope Producer (BLIP) became operational in 1973. Protons from the 

LINAC are sent via an underground beam tunnel to the BLIP facility where they strike various 

target metals. These metals, which become activated by the proton beam, are then processed at 

the Target Processing Laboratory for use in radiopharmaceutical development and production. 
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The targets are cooled by a continuously-recirculating water system. The BLIP facility 

underwent significant upgrades in 1996 in support of the Brookhaven Isotope Research Center 

(BIRC) program. The 200 MeV Proton Linear Accelerator serves as a proton injector for the 

AGS and also supplies a continuous beam of protons for radionuclide production by spallation 

reactions in the BLIP.

In 1982, the National Synchrotron Light Source (NSLS) began operation. The NSLS guides 

charged particles in an orbit. As the electrons spin inside a hollow donut-shaped tube called an 

electron storage ring, they give off light called synchrotron light. This light, which can be 

detected by specialized instruments, is used to study the properties of matter. The NSLS uses a 

linear accelerator and booster synchrotron as an injection system for two electron storage rings 

that operate at energies of 750 MeV vacuum ultraviolet (VUV), and 2.5 GeV (X-ray). The 

synchrotron radiation produced by their stored electrons is used for VUV spectroscopy and for 

X-ray diffraction studies.

Brookhaven’s newest accelerator facility is the Relativistic Heavy Ion Collider (RHIC), 

completed in 1999 (the large ring at the top of Figure 4-1).

Department of Applied Science/Nuclear Energy 

The Target Processing Laboratory (also called the Hot Laboratory in 1993) officially opened on 

January 15, 1951 and is still in use today. The original purpose of the central facility was to 

provide appropriately-shielded areas for research with large amounts of radioactive material. 

The “hot” area of the Hot Laboratory included five hot cells, three chemical-processing hot cells, 

and three high-level hot cells for handling and processing radioactivity in gaseous, liquid, or 

solid form.

The High Intensity Radiation Development Laboratory (HIRDL), which contained (in the early 

1970s) a million-curie range of Co-60 and Cs-137 sources, was used for source development and 

experimental process irradiations. A Co-60 pool in the HIRDL facility operated at lower activity 

levels into the 1990s. Currently, very little mission-specific work is occurring within the 

HIRDL.

Waste Management

Waste management has been intrinsic to BNL from the beginning of operations. In late 1949, 

the Health Physics & Safety Summary Monthly reports began to include a section titled “Waste 

Disposal” or “Waste Disposal and Reclamation,” and later, “Waste Management.” The group 

was composed of Safety and Environmental Protection (S&EP) personnel assisted by personnel 

from the Maintenance Department. The S&EP personnel remained quite constant over time, as 

seen in organizational charts captured from the site (BNL, 1960-1966). 
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4.2 Radiation Exposure Potential from Operations

Given the broad scope of BNL activities involving ionizing radiation, workers were potentially 

exposed to external photon, beta, and/or neutron radiation from a variety of sources. Potential 

sources included radioactive materials, nuclear reactors, particle accelerators, and X-raygenerating equipment.

4.2.1 Photon

Many BNL radiological operations involved gamma and X-ray photon radiation fields. Potential 

photon exposure sources to workers would have been associated with the following:

Gamma-emitting fission and/or activation products resulting from reactor and accelerator 

operations

Production and use of high-intensity gamma sources, typically Co-60 and Cs-137

Radioisotopes used in medical research and treatment

X-ray-generating machines

Calibration sources of americium, thorium, radium, cobalt, cesium, and other miscellaneous 

radionuclides

The very high-intensity sources were handled in a shielded configuration or shielded facility. 

Highly-contaminated or activated equipment was handled using standard health physics controls 

of time, distance, and shielding. 

4.2.2 Beta

BNL research and operations did not focus on activities with beta-particle-emitting source terms. 

However, beta radiation over a broad range of energies could have been encountered from 

activation and fission products from reactor and accelerator operations as well as other 

radionuclides, such as those used as calibration sources and for medical treatment and research. 

Whether a beta source is considered an internal hazard or both an internal and external hazard 

depends on the maximum energy of the beta emission for a given radionuclide, the shielding 

employed, and the use of protective clothing. Higher-energy beta-emitters present both an 

external hazard (to the skin) and an internal hazard. In many cases, beta-emitting radionuclides 

also emit characteristic photons.
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4.2.3 Neutron

There were many sources of potential neutron radiation exposure associated with BNL 

operations. The source of the neutron emissions from these activities and potential worker 

exposure would have been associated with the following:

Accelerators

Operating reactors, especially those designed to create neutron beams

Neutron-generating sources, either via the α,n reaction (PuBe, RaBe, PoBe) or via 

spontaneous fission sources (Cf-252)

The broad scope of BNL neutron-generating activities resulted in a correspondingly extensive 

neutron energy spectrum. The spectrum ranged from the thermal energy region of 0.025 eV 

through the fission spectrum of 0.1 to 6.0 MeV (predominant energy of 0.7 to 1.0 MeV), and 

included high energy, accelerator-produced neutrons greater than 14 MeV. Additional 

information is available in ORAUT-TKBS-0048.

4.2.4 Radioactive Source Materials

Many of the radioactive source materials handled at BNL were alpha-particle emitters. Although 

alpha particles do not present an external exposure hazard, the prevention of internal alpha 

exposures was recognized from the onset of site operations as the most significant radiological 

internal hazard protection challenge (BNL, 1947, pdf p. 2).

There were also a variety of beta- and beta-gamma-emitting radionuclides that were potential 

internal dose hazards at BNL. Table 4-1 provides a summary of radionuclides that are 

recognized as potential contributors to internal dose to BNL workers. This list is not 

all-inclusive, but it does include all of the most significant sources of internal radiation dose. 

Radionuclides that emit both alpha and beta(-gamma) are simply listed as alpha-emitters because 

the alpha emission will be the predominant component of the internal dose. Likewise, 

beta-gamma emitters are simply listed as beta emitters.
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Table 4-1: Potential Contributors to BNL Internal Dose and Their Primary Modes of Decay 

Radionuclide Primary Mode of Decay

H-3 Beta

Mixed Fission Products (MFP) Beta

Mixed Activation Products (MAP) Beta

Th-232 Alpha

Uranium Alpha

Plutonium Alpha

Am-241 Alpha

Po-210 Alpha

4.2.4.1 Uranium

Depleted and natural uranium compounds were commonly used in ton quantities at BNL. 

Uranium in various enrichments, including highly-enriched, was used in critical assemblies and 

reactors.

Approximately 110 tons of natural uranium fuel slugs were fabricated into aluminum-clad fuel 

rods by the BNL metallurgy group. During the operation of the BGRR (1950-1958), there were 

28 reported ruptures of BGRR fuel and one rupture of a uranium oxide (U3O8) sample that was 

being irradiated for the radioiodine-production program (ORAUT-TKBS-0048, pdf p. 20). 

Leaking or spent fuel elements were moved to a pool-type underwater storage area (“canal”) 

where they were chopped up for shipping for off-site disposal. Corrosion and oxidation of the 

natural fuel slugs occurred in the fuel transfer and storage canal. Over 2414 fuel elements 

generated during a 12-year period were shipped from the canal. The contaminated water, filter 

media, and back-flush from the ion exchange columns were pumped to the storage tanks at the 

Waste Concentration Facility, Building 811. In 1959, the natural uranium was replaced with a 

smaller enriched uranium core. The BGRR was partially decommissioned in 1972. The exhaust 

ducts from the reactor and to the stack have been sealed from the fans. The fans remain in their 

cells. The intake duct, exhaust duct, and fans are grossly contaminated from the fuel failures 

(ORAUT-TKBS-0048, pdf p. 21). The HFBR and MRR were operated with enriched uranium 

fuel. Both facilities have now been closed and the spent fuel sent off site. Un-irradiated fuel for 

the three reactor facilities was stored in secure vaults (DOE, 1996, pdf p. 39).

In about 1950, BNL started investigating the feasibility of processing spent fuel elements by 

dissolving them in fluorine-based interhalide compounds. After a laboratory study, a distillation 

plant was constructed in 1951; an engineering test facility was designed in 1953. On May 15, 

1957, a series of explosions of liquid bromine trifluoride, uranium hexafluoride, and uranium 

metal occurred in Building 801. One worker was seriously burned and several others were 

treated and released. Approximately 50 pounds of natural, un-irradiated uranium were released 

to the atmosphere (Volatility, 1957).
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Uranium was also used in critical assemblies for nuclear reactor research. Research and 

development on Liquid Metal Fuel Reactor (LMFR) technology took place in Building 820 from 

1957-75. A simulated reactor with a core of uranium dissolved in bismuth was studied 

(ORAUT-TKBS-0048, pdf p. 36). Radiation and Chemical Technology Buildings 526-527 

contained unknown quantities of uranium of various enrichments. This area originally housed a 

criticality facility for reactor physics (ERDA, 1977, pdf p. 48; Liverman, 1977). U-233 was used 

in the Th-U-233 Fuel Rod Development Program in 1962. ORNL was to fabricate and send 

1000 rods to BNL for study in its critical experiments facility. A total of approximately 30 kg of 

U-233 was in the uranium-thorium mixture (Special Nuclear, 1963). The U-233 generally 

contains U-232 as an unavoidable contaminant. In 1974, U-233 targets were irradiated at the 

cyclotron using alpha particles, but only in milligram amounts (Progress Report, September 

1974).

Uranium was fabricated into targets for irradiation in reactors and accelerators. The uranium 

was machined in the Hot Machine Shop (Building 530, replaced by Building 462). Uranium 

targets were reprocessed. For example, from March 1952 to June 1960 there was a program at 

the Hot Laboratory to produce I-131 by acid-dissolution of irradiated uranium samples. U-234 

foils (100 μg) were irradiated with deuterons to produce Pu-234 in 1975 (Hull, 1977).

Depleted uranium (DU) was used in target areas of the AGS (ORAUT-TKBS-0048, pdf p. 25). 

A muon shield consisting of over 15 tons of DU was set up for a 1966 AGS experiment (HP 

Summary, May 1966). DU was cleaned for an experiment at CERN (Conseil Européen pour la 

Recherche Nucléaire, or European Council for Nuclear Research) in 1985-86.

Building 1008 was the Uranium Calorimeter Factory in 1988. One calorimeter module housed 

fifty 102-inch by 25-inch uranium plates. There were enough plates to construct 20 modules 

(Lazo, 1988b). NIOSH has obtained no further information about what went on in this factory.

In 1995, an inventory showed that DU was present in eleven buildings in quantities from a few 

grams to nearly 27,000 kilograms. Natural uranium was located in four buildings in quantities 

from 10s of grams to nearly 85 kilograms (Miltenberger, 1995).

4.2.4.2 Fission and Activation Products

Fission and activation products have been present at BNL from the earliest days to the present. 

Some fission and activation products were the intended outputs of the BNL reactors and 

accelerators. For example, targets were irradiated to produce materials for basic research, 

medical research, or source manufacture. Other fission and activation products were produced as 

unintended byproducts of these operations; for example, activation of facilities and equipment, 

cooling air activation, or activation of contaminants in targets. BNL also imported fission and 

activation products from other AEC/DOE facilities and commercial sources.

By 1948, 25 different isotopes were already in use, well before the start of operations at the 

BGRR (Cowan, 1948). From March 1952 to June 1960, there was a program at the Hot 

Laboratory to produce I-131 by acid-dissolution of irradiated uranium samples. During the late 

1950s and early 1960s, a number of radioisotopes were in development and/or production at 
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what was then known as LEAF (Low Energy Accelerator Facility), which included the 

cyclotrons and the Van de Graaff accelerator (Flood, 1982). The primary purpose of these 

isotopes was medical research. In the 1970s, the BLIP was set up to use the excess capacity of 

the 200 MeV Linac to produce radionuclides for the development of new radiopharmaceuticals, 

mostly for diagnostic purposes. The Chemistry Linac Irradiation Facility (CLIF) operated in a 

similar way, but it was used for irradiations of a few hours or less (ERDA, 1977). The Hot 

Laboratory and other locations were used to process targets (ORAUT-TKBS-0048, pdf p. 40). 

In 1971-1972, the High Intensity Radiation Development Laboratory (HIRDL), which contained 

million-curie range Co-60 and Cs-137 sources, was used for source development and 

experimental process irradiations (ORAUT-TKBS-0048).

The above are just some examples of the many uses of fission and activation products used or 

produced at BNL. They ranged from small quantities of short-lived isotopes to significant 

quantities of long-lived material. Many of these activities only involved a few researchers in 

close contact with the materials. In addition, the isotopes produced for diagnostic medical use 

had short half-lives to reduce the dose to the patients. After discontinuation of the research, only 

the longer-lived material remained as residual contamination. Much of the equipment used was 

decontaminated or disposed of as waste. The primary exception was at the BGRR. In 2000, 

there were an estimated 1,400 Ci of Fe-55, 0.7 Ci of Co-60, 13 Ci of Sr-90, and 15.5 Ci of 

Cs-137 remaining in the BGRR complex due to operations with failed fuel (Musolino, 2000).

4.2.4.3 Tritium

Tritium was encountered in several forms: tritiated water (HTO), tritiated gas (HT), organicallybound tritium (OBT), and metal tritide (MT). H-3 appears to have been widely used in medical 

and biological research. Medical research involving OBTs started in the 1950s. Tritiated 

thymidine was injected into patients and animals in the mid-1960s (Flood, 1967). In 1967, bean 

plants were grown in 2 Ci/liter of HTO at Medical/Biology (HP Summary, April 1967). In 1969, 

after gross H-3 contamination of one of the organic chemistry labs, a reference states that urine 

samples and CAMs indicated that the form was H-3-labeled benzoic acid (HP Summary, April 

1969). There was a long-running experiment with mice in the 1970s and disposal of large 

quantities of contaminated mouse litter was reported monthly (Progress Reports, 1974).

In 1972, H-3-contaminated vacuum pump oils were a problem, especially at the 3.5 MeV 

Physics/Chemistry Van de Graaff (Flood, 1972). When tritium ions were accelerated, 

approximately 200 Ci/month of HT was used (ERDA, 1977). The Hot Laboratory fabricated 

H-3 into accelerator targets. The tritium targets were used at the 18-inch cyclotron, the 50 MeV 

AGS LINAC, the 3.5 MeV Van de Graaff, the Tandem Van de Graaff, and the 200 MeV 

LINAC. Accelerator targets were in the form of SMTs, such as zirconium tritide. At Building 

919 in 1973, the 80-inch bubble chamber facility had a 250 mCi gas chromatograph source as 

well as other sources up to 100 mCi (Bubble Chamber, 1973). Cooling water at the AGS 

became tritiated, especially at the target stations. The levels ranged from 1,000 pCi/L to 400,000 

pCi/L. These were closed systems that were drained prior to 2009 (Lessard, 2009).
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The amount of H-3 on site increased dramatically with the HFBR start-up in 1965. The HFBR 

was a 30-60 MW thermal heavy-water-moderated nuclear research reactor. Heavy water flowing 

in the core was exposed to a dense neutron field that activated the deuterium atoms in the water 

to produce tritium. The typical concentration was about 2 mCi of H-3 per cm3of heavy water. 

The form was HTO, and this was the most important source of H-3 exposure at BNL from 1965 

to 1999. The second most important source was probably the 3.5 MeV Van de Graaff where H-3 

tritium beams and targets were frequently used. High-beam currents of protons or deuterons 

would cause the H-3 to diffuse out of the zirconium targets and into the beam pipe and the 

surrounding area. Substantial build-up of contamination was noted in 1970 (HP Summary, 

February 1970). During the change-out of a leaking H-3 source bottle in 1971, levels reached 

2000 MPC in the area of leak. However, the highest exposure to the workers involved was only 

24 mrem (HP Summary, October 1971).

4.2.4.4 Thorium

Thorium was present at BNL starting in the 1950s, and was used primarily in nuclear 

engineering research. All references to thorium at BNL are to natural thorium (Th-232-series). 

Control and accountability procedures were set up indicating that thorium was to be handled as a 

source material like uranium (BNL, 1948; Fox, 1950). In 1959, a study was made of ThO2

hazards as a result of the increased use of this material in the Nuclear Engineering Laboratory 

(HP Summary, May 1959). The MPC of 4x10-12 μCi/cm2was taken from a proposed revision of 

NBS Handbook 52, making it “very hazardous”; appropriate arrangements were being made for 

containment and monitoring. Various chemical compounds and physical forms (including 

dispersible powders) were present (BNL, October 1957; BNL, December 1957; HP Summary, 

February 1959; Progress Report, March 1952; Progress Report, April 1952; Progress Report, 

May 1952; Progress Report, October 1952; Progress Report, November 1953; Progress Report, 

December 1953; Progress Report, June 1954; Progress Report, August 1954; Rice, 1966). 

There is evidence that thorium operations were monitored by health physics staff. For example, 

in 1969, among the operations monitored was the change-out of filters in line with a Th-228 

molecular beam apparatus in Chemistry (HP Summary, October 1969). In 1971, thorium foils 

were used in studies for a fission track personnel dosimeter (HP Summary, September 1971). In 

the mid-1970s, a “thorium cow” was in use at Bldg. 510. This is a device that concentrates the 

daughter products from thoron (notably Pb-212) by precipitation on a charged electrode. This 

device was used to produce calibration sources and at the Tandem Van de Graaff (Progress 

Report, January 1974; Progress Report, November 1975; Progress Report, December 1975). In 

1986, five workers in the Department of Applied Science working with “thorium series 

(magma)” were identified for whole body counts (Lukas, 1986), indicating that a small thorium 

program still existed (magma apparently referred to geothermal-research-related samples 

containing trace amounts of thorium). An inventory of dispersible radioactive material in 1997 

indicated that only microcurie amounts were still on site (Flores, 1998).
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4.2.4.5 Plutonium

Plutonium was among the first safety concerns at BNL, probably because its hazards were well 

known by the time BNL was established. Its early uses are not well described, but seemed to 

involve studying its various properties. Due to the activation of uranium, plutonium was present 

in the fuel of the operating reactors; however, BNL fuel was sent to other sites for reprocessing 

(Van Horn, 1962-1963). Nevertheless, plutonium was present in the residual contamination of 

some facilities, particularly the BGRR, which had a history of operations with failed natural 

uranium fuel elements. There was also Pu in the fission product mixture processed by the waste 

handlers (HP Summary, March 1949). Plutonium was also contained in neutron sources at 

Medical, Chemistry, and the calibration facility (ORAUT-TKBS-0048, pdf p. 94).

The following list briefly summarizes known occurrences involving Pu at BNL:

In January 1963, a leaking glass carboy containing gold in a solution contaminated with 

plutonium was received at BNL (AEC, 1963, pdf p. 68). 

In December 1963, plans were being prepared for the conversion of a gamma facility in the

Hot Lab to a plutonium metallurgy laboratory to perform physical and chemical tests on cold 

and irradiated plutonium carbide fuels (Progress Report, December 1963). 

In 1966, a lathe contaminated with U-235 and Pu-239 (originally from Mallinckrodt) appears 

to have been used in the shops at BNL, (HP Summary, January 1966).

In 1966, plutonium was also used in nuclear engineering research in the critical assembly 

area; plans were designed to prevent surface or airborne contamination or damage to the 

encapsulated source material (HP Summary, March 1966).

In March 1967, four grams of Pu-239 in the forms of oxide and carbide were introduced into 

one of the glove boxes at the Hot Lab. The experiment consisted of vaporization of oxide in 

a closed system. The operation was reviewed and covered by health physics (Progress 

Report, February 1967). 

In 1970, three Pu vaporization experiments were conducted in the alpha-gamma facility (HP 

Summary, February 1970).

In June 1971, 61 PuO2-UO2 pellets containing 439 grams of Pu were encapsulated by the Hot 

Lab health physics personnel in a new glove box facility set up for this purpose (HP 

Summary, June 1971).

By September 1971, plutonium work at the Hot Lab appears to have ended since some of the 

equipment was being converted to use in the chemical processing of BLIP targets at the Hot 

Lab (HP Summary, September 1971).
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In 1996, there were still gram quantities of plutonium stored in an SNM vault (DOE, 1996, 

pdf p. 40).

In 2000, a total of 1.22 Ci plutonium isotopes were estimated to remain in the BGRR 

complex (Musolino, 2000).

4.2.4.6 Americium

Americium is generally present at BNL as a byproduct of plutonium production/irradiation. 

There is also evidence that operations involving purified Am-241 took place on site during the 

time period under evaluation. In 1959, an Am-241-contaminated dry box from the criticality 

facility was partially cleaned prior to storage (HP Summary, May 1959). Americium sources 

were also used for calibrations (HP Summary, October 1964; HP Summary, April 1965; HP 

Summary, June 1965) and X-ray fluorescence studies (Progress Report, Oct-Nov 1983). In 

1966, americium “in sizable amounts” was to be used in the critical assembly area; plans were 

designed to prevent surface or airborne contamination or damage to the encapsulated source 

material (HP Summary, March 1966). There is no subsequent mention of this material, which is 

likely an indication that no problems were experienced. Site interviews indicate that since 1989 

Am-241 has only been present in μCi amounts for research projects (Personal Communication, 

2008). An inventory of dispersible radioactive material in 1997 indicated that only microcurie 

amounts were still on site (Flores, 1998). However, it may still be present in residual 

contamination with plutonium isotopes. In 2000, a total of 0.072 Ci of Am-241 was estimated to 

remain in the BGRR complex (Musolino, 2000).

4.2.4.7 Polonium

Polonium was among the first radionuclides received at BNL. Apparently, polonium sources 

were initially used due to security issues associated with using plutonium sources (HP Summary, 

October 1949). The two most common uses appear to have been as an alpha source for basic 

research and as a Po-Be neutron source for calibrations and other purposes. The hazards of 

polonium were recognized early on; in 1947, safety precautions were published by groups using 

polonium sources (Salant, 1947).

A Po-Be source was requested as early as 1947 (Hayner, 1947). There was a 1949 request for a 

replacement polonium source to be used in a spectrometer (Lancaster, 1949). Initially, the 

sources were constructed using a thin nickel plating that could allow the polonium to diffuse 

through it, and some of these sources leaked (Cowan, 1947; Progress Report, April 1965). Two 

individuals acquired 20% of the maximum permissible body burden (MPBB) from an incident in 

August 1960 (Haworth, 1960; HP Summary, January 1961). In 1963, the Chemo Nuclear group 

worked with 10-Ci polonium sources. The operations manual for this work was reviewed by 

health physics and emergency instructions were brought up-to-date prior to use. Instrumentation 

for monitoring these experiments was checked and found to be in working order (Progress 

Report, September 1963). A Po-210 contamination incident also occurred on December 21, 

1964 (Progress Report, January 1965). A physics experiment that involved 297 mCi of Po-210 

was planned in 1966 (HP Summary, March 1966). The material was to be dissolved in 

hydrofluoric acid, placed in a sealed container in the alpha dry box at the Hot Lab, and then 
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transferred to the Physics lab in a sealed bag. Documentation has not been located that indicates 

whether the experiment took place. An inventory of dispersible radioactive material in 1997 

indicated that only microcurie amounts were still on site (Flores, 1998).

4.3 Time Period Associated with Radiological Operations

Per the DOE Office of Health, Safety and Security, the time period associated with DOE 

operations at the Brookhaven National Laboratory is from 1947 to present. There is already an 

existing class in the SEC for BNL from January 1, 1947 through December 31, 1979, a period 

that is not included in this evaluation. Beginning in 1980, internal dosimetry was no longer filed 

in individual worker files. The records repositories were group-specific and this decentralization 

of records has inhibited the efficient collection of complete sets of internal dosimetry records for 

the purpose of this evaluation. 

Although an internal monitoring program appears to have been active throughout the period 

under evaluation, the program was not formally documented (Implementation Plan, 1991). 

Through its research and reviews, NIOSH has identified an internal monitoring procedure 

drafted by BNL in August 1993 (Reciniello, 1993). Although documentation available to 

NIOSH suggests there was an operational internal monitoring program during the period under 

evaluation, personnel data management practices (i.e., lack of centralized databases) preclude the 

summarization and presentation of total internal monitoring data availability. This is an issue at 

least up to the period when the internal monitoring procedure was implemented in 1993. 

An assessment performed by the DOE Chicago Operations Office in December 1993 found the 

BNL HP program “in compliance with applicable DOE standards and acceptable professional 

practices.” This assessment detailed the level of compliance for the external dosimetry program, 

the internal dosimetry program, the radiation and contamination survey program, and the 

personnel radiological records program (HP Assessment, 1993). 

4.4 Site Locations Associated with Radiological Operations

Among the major scientific facilities operated at the Laboratory to carry out the various scientific 

programs during the time period under evaluation were:

The High Flux Beam Reactor (HFBR) that was fueled with enriched uranium, moderated and 

cooled by heavy water, and operated at a routine power level of 40 MW.

The Medical Research Reactor (MRR), an integral part of the Medical Research Center 

(MRC) that was fueled with enriched uranium, moderated and cooled by natural water, and 

operated intermittently at power levels up to 3 MW.

The Alternating Gradient Synchrotron (AGS), a proton accelerator that operated at energies 

up to 33 GeV.
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The 200 MeV Proton Linac, that served as an injector for the AGS. It also supplied a 

continuous beam of protons for radionuclide production by spallation reactions in the 

Brookhaven Linac Isotopes Production Facility (BLIP) and in the Chemistry Linac 

Irradiation Facility (CLIF).

The Tandem Van de Graaff, Vertical Accelerator, and Chemistry Van de Graaff, that were 

used in medium-energy physics investigations as well as for special radionuclide production.

The National Synchrotron Light Source project, that used a linear accelerator and booster 

synchrotron as an injection system for two electron storage rings operating at energies of 700 

MeV vacuum ultraviolet (VUV) and 2.5 GeV (X-ray). It was used for spectroscopy in the 

VUV ring and for diffraction studies in the X-ray ring.

Although the above listed areas are specifically identified for the use of AEC-related radiological 

materials, documentation available to NIOSH does not indicate any definite boundaries between 

radiological and non-radiological areas for the period being evaluated. NIOSH is therefore 

unable to define individual worker exposure scenarios based on specific work locations within 

the Brookhaven National Laboratory site during the period under evaluation. Based on this 

information, NIOSH has considered all work areas in its review of BNL for this evaluation. 

4.5 Job Descriptions Affected by Radiological Operations

The Personnel Monitoring Policy was to provide a radiation dosimeter to all workers who had 

the potential to receive external exposure (HP Procedures, 1948; Personnel Monitoring, 1948; 

Personnel Monitoring, unknown date; Pocket Chambers, 1952; Safety Manual, 1948; Use of 

Dosimetry, 1995). This policy was implemented by designating facilities that used radioactive 

materials or created radiation sources as “radiation areas” and requiring that all who entered must 

have a radiation dosimeter. The available records clearly indicate that this policy was being 

implemented throughout the operating history. However, this resulted in a segment of workers 

who were not externally monitored and for whom no radiation exposure records are available. 

This is consistent with industry practice, as there would have been workers whose duties did not 

require them to be near a radiation source and would not have been expected to have received 

radiation exposure in the location of their normal work assignment.

It should be noted that AEC/ERDA/DOE requirements specified that only those individuals 

expected to exceed 10% of the annual dose limit (or later, exceed 100 mrem/y) were required to 

be monitored. Some examples of the types of workers who may not have been monitored 

include: those in administrative positions whose normal work location was not in one of the 

facilities with designated radiation areas; construction trade workers whose projects were located 

in non-radiation areas; and engineers or scientific personnel whose duties did not require that 

they enter a radiation area. Personnel dosimeter monitoring data will not be available for such 

types of workers.
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Through the course of ongoing dose reconstruction and research, NIOSH has determined that, 

due to undocumented worker movements across the site and limited claimant-specific 

information pertaining to work locations, it is unable to eliminate any specific worker from 

potential exposure scenarios based on assigned work location. NIOSH has found that a 

determination cannot always be made as to whether or not an employee worked in technical 

areas with a history of radioactive material use, or whether an employee should have been 

monitored for radiological exposures. 

NIOSH has determined that the site-specific and claimant-specific data available for Brookhaven 

National Laboratory for the time period under evaluation are insufficient to allow NIOSH to 

determine that any specific work group was not potentially exposed to radioactive material 

releases or possible subsequent contamination.

NIOSH has insufficient information associating job titles and/or job assignments with specific

radiological operations or conditions. Without such information, NIOSH is unable to define 

potential radiation exposure conditions based on worker job descriptions. Based on this 

information, NIOSH has considered all job titles/duties in its review of BNL for this evaluation.

5.0 Summary of Available Monitoring Data for the Proposed Class

The primary data used for determining internal exposures are derived from personal monitoring 

data, such as urinalyses, fecal samples, and whole-body counting results. If these are 

unavailable, the air monitoring data from breathing zone and general area monitoring are used to 

estimate the potential internal exposure. If personal monitoring and breathing zone area 

monitoring are unavailable, internal exposures can sometimes be estimated using more general 

area monitoring, process information, and information characterizing and quantifying the source 

term.

This same hierarchy is used for determining the external exposures to the cancer site. Personal 

monitoring data from film badges or thermoluminescent dosimeters (TLDs) are the primary data 

used to determine such external exposures. If there are no personal monitoring data, exposure 

rate surveys, process knowledge, and source term modeling can sometimes be used to 

reconstruct the potential exposure.

A more detailed discussion of the information required for dose reconstruction can be found in 

OCAS-IG-001, External Dose Reconstruction Implementation Guideline, and OCAS-IG-002, 

Internal Dose Reconstruction Implementation Guideline. These documents are available at: 

http://www.cdc.gov/niosh/ocas/ocasdose.html.
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5.1 Data Capture Efforts and Sources Reviewed 

As a standard practice, NIOSH completed an extensive database and Internet search for

information regarding Brookhaven National Laboratory. The database search included the DOE 

Legacy Management Considered Sites database, the DOE Office of Scientific and Technical 

Information (OSTI) database, the Energy Citations database, the Atomic Energy Technical 

Report database, and the Hanford Declassified Document Retrieval System. In addition to 

general Internet searches, the NIOSH Internet search included OSTI OpenNet Advanced 

searches, OSTI Information Bridge Fielded searches, Nuclear Regulatory Commission (NRC) 

Agency-wide Documents Access and Management (ADAMS) web searches, the DOE Office of 

Human Radiation Experiments website, and the DOE-National Nuclear Security AdministrationNevada Site Office-search. Attachment 1 contains a summary of Brookhaven National 

Laboratory documents. The summary specifically identifies data capture details and general 

descriptions of the documents retrieved.

In addition to the database and Internet searches listed above, NIOSH identified and reviewed 

numerous data sources to determine information relevant to determining the feasibility of dose 

reconstruction for the class of employees under evaluation. This included determining the 

availability of information on personal monitoring, area monitoring, industrial processes, and 

radiation source materials. The following subsections summarize the data sources identified and 

reviewed by NIOSH.

Detailed information regarding NIOSH’s data capture efforts for the Brookhaven National 

Laboratory can be found in the related NIOSH evaluation report for SEC-00113 (NIOSH, 2009). 

5.2 Worker Interviews

To obtain additional information in support of its 2009 evaluation of Petition SEC-00113, 

NIOSH interviewed nine former Brookhaven National Laboratory employees. Details regarding 

these interviews can be found in the SEC Petition Evaluation Report for Petition SEC-00113, 

Brookhaven National Laboratory (NIOSH, 2009). Additional interviews for the specific purpose 

of supporting this evaluation were not deemed necessary, and therefore, were not performed. 
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5.3 Internal Personnel Monitoring Data

The majority of the available internal monitoring data applicable to the evaluation time frame 

still exists in hard copy form, resides in multiple locations, and is primarily sorted into individual 

employee files. Consequently, a definitive assessment of total monitoring data available would 

only be possible through the perusal and tallying of each file’s contents. Constraints on the 

retrievability of the data from the site, especially for internal monitoring data prior to 1980, 

precluded NIOSH’s accomplishment of this task. However, NIOSH has extracted and 

electronically entered monitoring data found within the approximately 2300 documents that were 

captured from the site and other sources as of May 2009. Furthermore, NIOSH conducted two 

additional data capture exercises focused specifically on retrieving monitoring data from 

individual worker files; data available within those captured files has been summarized in this 

evaluation.

The results of the NIOSH data capture efforts provide the basis for the observed data availability 

summaries presented in the following subsections. It is important to remember that the data 

presented do not represent the actual total available monitoring data, but rather, a subset that was 

available within the retrieved documents. Therefore, the captured results expectably indicate 

temporal and data quantity gaps. Nevertheless, when coupled with numerous captured 

documents describing BNL health and safety practices, the retrieved data provide additional 

support for the existence of a comprehensive and conscientious worker monitoring program 

appropriately based on exposure potential. However, personnel monitoring data retrievability 

issues, which are compounded by the site’s record-keeping practices over the years, present the 

most significant issues affecting this report’s evaluation. It is apparent that there was a turning 

point in the BNL radiological program and record-keeping requirements at the beginning of 1980 

(following a 1979 site assessment). Based on this information, the assessment of NIOSH’s 

ability to bound dose for the class under evaluation is primarily focused on the ability of the site 

(or other applicable entity) to identify, retrieve, and provide (to NIOSH) the applicable BNL 

personnel internal and external monitoring data.

For much of the site’s operational history, department/division health physics representatives 

designated personnel for participation in the internal dosimetry program (WBCs and/or 

urinalysis) using professional judgment. This judgment could also have included monitoring 

frequency (BNL, 1995; Holeman, 1999). Table 5-1 summarizes in vivo and in vitro monitoring 

practices and data storage media throughout the operational history of the laboratory. In general, 

in vivo and in vitro dosimetry was performed for initial employment checks, annual physicals, 

for employees engaged in higher-exposure-potential work, and incidents. Details regarding the 

various analyses used and the associated minimum detectable activities are presented in the BNL 

TBD for Occupational Internal Dose (ORAUT-TKBS-0048).
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Table 5-1: Internal Dosimetry Timelines and Data Source Descriptions

Type Dates Description

In vivo

1960 - 1991

Outputs are available from the whole-body counting system that was in place 

at the time (several whole-body counting systems were in place during this 

time period). This hard copy output is kept in personnel dose history files, 

some log books, and some medical records.

1992-present

In vivo bioassay performed routinely for Reactor Division personnel, Waste 

Management personnel, BLIP, Facility Support personnel, and 

Environmental Restoration personnel. These data are all available as hard 

copy reports from the PM Whole Body Counter.

1999-present

In vivo bioassay data are also available electronically on the workstation of 

the Whole Body Counting System. The data have been exported and 

provided to NIOSH (“ABACOS2K” files). The data indicate that 2815 

counts were performed on 963 individuals.

In vitro

1947- 1984 Results were manually kept in hard copy in different formats. This hard 

copy is kept in personnel dose history files.

1984- 2003 In vitro bioassay performed for RD personnel. 1984-1995 tritium dose data 

were sent to Landauer and recorded in the Landauer System. Data are 

available on microfiche and have been entered into a spreadsheet by NIOSH. 

Many tritium monthly summaries from 1992-1999 are available in hard 

copy reports. The tritium data are primarily in terms of dose. Urinalysis 

data consisting of over 11,000 tritium results and a few gamma scans from 

the on-site Analytical Services Laboratory (“ASL” Access database) have 

been captured for the period 1995-2003.

1999- present After 1999, hard copy records of all in vitro bioassay results are maintained 

in the whole body counter office. After 2000, electronic versions are also 

available and have been captured by NIOSH.

Other 1998-present Doses from intakes are recorded in HPRS. Doses could be the result of 

either in vivo or in vitro bioassay or assigned from air samples.

Source: NIOSH, 2009

Attachment 1 of the evaluation report for SEC-00113 (NIOSH, 2009) presents a summary of 

whole body counts and urinalysis monitoring data pulled from documents that NIOSH captured 

during the initial general-evaluation data capture events (as of May 1, 2009), plus results 

obtained from two later data-pedigree-focused efforts. Results in Attachment 1 have been 

presented in terms of the number of employees monitored per year. Extraction and entry of 

individual analytical results was performed only for data found in documents captured prior to 

May 1, 2009 (over 2,300 documents at that time). These individual analytical results are 

presented and discussed in the following two subsections. 
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Although an internal monitoring program appears to have been active throughout the period 

under evaluation, the program was not formally documented (Implementation Plan, 1991). 

Through its research and reviews, NIOSH has identified an internal monitoring procedure 

drafted by BNL in August 1993 (Reciniello, 1993). Although documentation available to 

NIOSH suggests that there was an operational internal monitoring program during the period 

under evaluation, personnel data management practices (i.e., lack of centralized databases) 

preclude the summarization and presentation of total internal monitoring data availability. This 

is an issue at least up to the period when the internal monitoring procedure was implemented in 

1993. 

An assessment performed by the DOE Chicago Operations Office in December 1993 found the 

BNL HP program “in compliance with applicable DOE standards and acceptable professional 

practices.” This assessment detailed the level of compliance for the external dosimetry program, 

the internal dosimetry program, the radiation and contamination survey program, and the 

personnel radiological records program (HP Assessment, 1993).

5.3.1 Urinalysis Monitoring Data

As mentioned above, Attachment 1 of the evaluation report for SEC-00113 contains a 

compilation of the available in vitro bioassay results from the SRDB documents collected and 

posted by NIOSH as of May 1, 2009. The raw data compilation contains just under 9100 

individual urinalysis sample results from 1049 individuals. Though many documents were used 

as data sources, a large portion of the internal data captured have come from two sets of 

urinalysis records from 1952-1975 (Urinalysis Records, 1952-1975a; Urinalysis Records, 1952-

1975b). These documents contain handwritten bioassay records for individual employees who

were terminated. The records appear to include all bioassay results for each employee listed 

within the documents, not just their termination results. Of the results collected, 87% were 

surveys, 7% were incidents, 5% were unknown, and 1% were re-checks.

In general, results include the employee’s name and at least one identifier such as “BNL Life 

Number,” division/department, and/or a location indicator. Major work groups identified 

included: 

Accelerator

Biology, Chemistry, and Physics

Critical Assembly, Department of Applied Science, and Nuclear Engineering

Health Physics, Safety & Environmental Protection, and Waste Management

Hot Lab and Medical

Plant Maintenance and Shops

Pile and Reactor
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The “BNL Bioassay Record” (Form 1720) was used from 1951 to 1967 and includes MFP, 

Sr-90, H-3, and alpha column headers. The other form used from 1952 to 1976 is titled 

“Urinalysis Record” and includes gross (gamma), Sr-90, and Po-210 column headers. There is 

also a “Gross Activity” form (BN-945), a “BNL H-3 Exposure Evaluation” form, and memos 

that detail incident follow-ups. Other radionuclides that were monitored for specific incidents 

included:

Ag-110 Na-24

Am-241 P-32

Au-198 Ra-226

Ce-141/143 (urine and fecal) Ru-106

Co-60 U-233

Hf-181 Zn-65

5.3.2 Whole Body Counting Data

During this evaluation process, NIOSH captured and entered over 1900 individual WBC results 

from 686 individuals. The data range from 1960 (the start of whole-body counting at BNL) to 

2000, after which the data are kept in the HPRS. The majority of the captured data are from the 

1980s; currently, data gaps exist for the years 1963, 1965-69, 1971, and 1991.

The data came primarily from several sets of whole-body results (WBC Summaries, 1987; 

Whole-Body Results, 1973-1981; Whole-Body Results, 1975-1981; Whole-Body Results, 1979-

1986; Whole-Body Results, 1988-1994; Whole-Body/Thyroid Results, 1983-1984). Much of the 

data was compiled from memos written from WBC program managers to S&EP representatives 

when they forwarded the WBC results for employees working in their respective areas. 

Typical radionuclides measured included: Cs-137, Co-58/60, Zn-65, Fe-59, Mn-54, and Be-7. 

There are also results for Cs-134, Ce-141/144, Ba/La-140, and the radioiodines. Results for lung 

and thyroid dose were also captured.

In general, results include the employee’s name and at least one identifier such as “BNL Life 

Number,” division/department, and/or a location indicator. There is some uncertainty regarding 

the WBC identifiers and work locations, but the data were cross-matched with the in vitro data or 

organizational charts when possible. Major work groups identified included:

Accelerator

Biology, Chemistry, and Physics

Critical Assembly, Department of Applied Science, and Nuclear Engineering

Health Physics, Safety & Environmental Protection, and Waste Management

Hot Lab and Medical

Plant Maintenance and Shops

Pile and Reactor
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5.4 External Personnel Monitoring Data

From the beginning of operations that may have involved radioactive material (in 1947), 

exposure to external radiation appears to have been consistently monitored throughout all years 

of operation at BNL. Table 5-2 summarizes the period of use, type of dosimeter, MDL, and 

exchange period.

Table 5-2: Minimum Detectable Levels for Photon, Beta, and Neutron Dose

Period of Use Dosimeter MDL (mrem)a Exchange Frequency

Start-up through 1954 Multi-element film + NTA 40 Weekly

Monthly

1955 through 1995 Multi-element film +NTA 30 Monthly

1996 to present Harshaw 8814 and 8806 TLD 

+ CR-39

10 Monthly

Start-up through 1995 NTA filmb~50 Weekly

Monthly

1996 to present CR-39b~20 Monthly

Source: ORAUT-TKBS-0048

a Estimated MDLs for each dosimeter in the workplace even though many doses were reported at less than the 

MDL.

b

Processing done by R. S. Landauer. 
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Table 5-3 provides a more specific listing of the types of monitoring performed at various times 

throughout BNL’s history, the methods/materials used, how the data were recorded, and in what 

manner the data are available for retrieval for creating a worker’s exposure history. The table 

shows that BNL periodically changed the monitoring methods to adopt better technologies for 

performing personnel monitoring.

Table 5-3: External Dosimetry Timelines and Data Source Descriptions

Type Dates Description

Whole Body 

Badges

1947- 1965 BNL film badges: BNL read its own data and recorded data on personnel 

cards.

1965- 1984 BNL film Badges: BNL read its own data and recorded data in a computer. 

These data are now available only in hard copy.

1985- 1995

Landauer read Landauer film badges and stored data on their system. 

These data are now available on microfiche and paper monthly reports. 

Summary data for lifetime Dose of Record for personnel have been entered 

in HPRS.

1996 –present BNL implements TLDs, reads its own badges, and stores data in HPRS.

Ring Dosimetry

1947- 1965 BNL ring badges: BNL read its own data and recorded it on personnel 

cards.

1965- 1984 BNL ring badges: BNL read its own data and recorded it in a computer. 

These data are available only in hard copy.

1985- 1995 Landauer read Landauer rings and stored data on their own system. These 

data are now available on microfiche.

1996 –present Landauer read Landauer rings and transmitted the data to BNL. These data 

are stored in HPRS.

Environmental 

Monitoring

1947 – mid 

1998

4 TLD-200 (calcium fluoride) 1cm x 1cm chips placed in a brass sphere 

which was then placed in a small plastic bottle with string attached.

Mid 1998 –

present

Harshaw 8807 with TLD 2211 cards.

Area Monitoring

1947- 1965 BNL film badges: BNL read its own data and recorded it on personnel 

cards.

1965- 1984

BNL film badges: BNL read its own data and recorded it in a computer. 

These data are now available only in hard copy. Landauer read Landauer 

badges and stored data on their own system; these data are now available 

on microfiche. Summary data for personnel have been entered in HPRS.

1996 –present BNL implements TLDs, reads its own badges, and stores the data in HPRS.

Neutron 

Dosimetry

Pre-1984 BNL whole-body film badges used NTA films for neutron measurement.

1985 - 1995 Landauer whole-body badges used combinations of NTA films, CR39, and 

Lexan for neutron monitoring.

1996 - present

BNL Harshaw 8806 TLD badges used a TLD-600 element in all badges 

with the addition of Landauer-supplied CR39 and Lexan (discontinued 

after June 1997) when high-energy neutron monitoring at the Alternating 

Gradient Synchrotron (AGS) was desired.
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Although the generally decentralized nature of BNL’s radiation monitoring program has resulted 

in difficulty obtaining complete historical internal monitoring data sets, external monitoring 

summary data are available for the entire evaluation time period with the exception of the 

summary report for 1971. External results for individual employees are available for 1971, but 

the annual summary report was not discovered during the NIOSH data capture efforts. 

Radiation exposure data were submitted annually to the AEC/ERDA/DOE in accordance with 

reporting requirements. Attachment 2 of the evaluation report for SEC-00113 (NIOSH, 2009) 

displays these data (except for 1971) and demonstrates that a significant number of workers were 

monitored every year. These data (from 1974 to 2007) were collected from the annual reports 

available on the DOE REMS website, and from similar annual reports found among BNL 

records (prior to 1974) (AEC, 1970; AEC, 1972; AEC, 1973; WBC Summary, 1960; WBC 

Summary, 1961; WBC Summary, 1964; Whole-Body Results, 1965-1969).

Figure 5-1 shows the dose distribution in the monitored population, indicating the maximum 

exposure range measured each year as well as the average exposure received by individuals with 

measureable exposure. Data provided to AEC/ERDA/DOE are reported in terms of individuals 

receiving a dose within a given range with 1 rem increments. The Maximum Dose Range 

presented in Figure 5-1 represents the maximum range for which at least one individual had a 

reported dose. Average dose data were not available in the summary reports for the years 1958-

65 and 1971-73. Figure 5-1 shows that the maximum exposure range went from around 7-9 rem 

in the late 1950s down to around 4-5 rem from 1963 through the 1970s, and then slowly ramped 

down through the 1980s (2-4 rem) and 1990s (0-2 rem). Since 1990, the maximum exposure 

range has been 0-1 rem. For those years for which average dose data are available, the values 

were around 1-2 rem until 1980, after which the averages were generally below 1 rem.
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0.000

0.200

0.400

0.600

0.800

1.000

1.200

1.400

1.600

1.800

2.000

0

1

2

3

4

5

6

7

8

9

1 0 1958 1959 1960 1961 1962 1963 1964 1965 1966 1967 1968 1969 1970 1971 1972 1973 1974 1975 1976 1977 1978 1979 1980 1981 1982 1983 1984 1985 1986 1987 1988 1989 1990 1991 1992 1993 1994 1995 1996 1997 1998 1999 2000 2001 2002 2003 2004 2005 2006 2007 Average Dose (rem) Maximum Dose Range (rem)

Year

Maximum External Dose Range and Average Dose by Year

Maximum Dose 

Range (rem)

Average Dose 

(rem)

Source: Data extracted from the following references: AEC, 1970; AEC, 1972; AEC, 1973; WBC Summary, 1960; WBC Summary, 1961; WBC Summary, 

1964; Whole-Body Results, 1965-1969.

Figure 5-1: Maximum External Dose Range and Average Dose by Year
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The Personnel Monitoring Policy was to provide a radiation dosimeter to all workers who had the 

potential to receive external exposure (HP Procedures, 1948; Personnel Monitoring, 1948; Personnel 

Monitoring, unknown date; Pocket Chambers, 1952; Safety Manual, 1948; Use of Dosimetry, 1995). 

This policy was implemented by designating facilities using radioactive materials or creating radiation 

sources as “radiation areas” and requiring all who entered to have a radiation dosimeter. The 

available records clearly indicate that this policy was being implemented throughout the operating 

history. However, this resulted in a segment of workers who were not externally monitored and for 

whom no radiation exposure records are available. This is consistent with industry practice, as there 

would have been workers whose duties did not require them to be near a radiation source and would 

not have been expected to have received radiation exposure in the location of their normal work 

assignment. 

It should be noted that AEC/ERDA/DOE requirements specified that only those individuals expected 

to exceed 10% of the annual dose limit (or later, exceed 100 mrem/y) were required to be monitored. 

Some examples of the types of workers who may not have been monitored include: those in 

administrative positions whose normal work location was not in one of the facilities with designated 

radiation areas; construction trade workers whose projects were located in non-radiation areas; and 

engineers or scientific personnel whose duties did not require that they enter a radiation area. 

Personnel dosimeter monitoring data will not be available for such types of workers.

NIOSH has identified that personnel dosimeter monitoring data for reconstructing external doses are 

available for the entire time that BNL has been operational. These data include extensive external 

monitoring results, including neutron exposure data.

5.5 Workplace Monitoring Data

As a part of BNL’s radiation protection program, it is evident that extensive monitoring of airborne 

radioactive dust has been regularly performed. In addition, air monitoring for tritium was performed 

and charcoal cartridges were used to sample for iodines. Information supporting these conclusions 

can be found in many captured documents. For example:

Air Samples provides results for air samples taken during an operation that welded percussion pins 

onto uranium plates (Lazo, 1988a).

Respirator Use by RCG Personnel discusses air samples taken to verify that respiratory protection 

was not required (Reciniello, 1992).

Burns & Roe was contracted by BNL to conduct an appraisal of airborne monitoring in 1991. The 

appraisal identified where airborne monitoring was satisfactory, where some improvements were 

desirable, and where airborne monitoring was not required because only small amounts of 

radioactivity were being used in the operations (BNL, 1990-1991a; BNL, 1990-1991b).
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Although evidence of an extensive air monitoring program has been found, very few monitoring 

results from this program have been located. As indicated in the references above, results for a few 

isolated situations have been located, but data that reflect the daily air sampling results that would be 

needed to reconstruct potential worker exposure have not been located. The evidence suggests that, in 

general, airborne issues at the reactors, labs, and accelerators were very infrequent, thus resulting in a 

casual approach to record-keeping. The inability to locate comprehensive results limits the viability 

of using air monitoring results in the dose reconstruction process. Considering the limited air 

monitoring data available for the site at this time, further assessment of potential internal dose using 

air sample data will not be included in this evaluation report.

5.6 Radiological Source Term Data

Sources of radiation doses to members of the evaluated class included, but were not limited to, 

plutonium, uranium, tritium, fission and activation products, transuranic radionuclides, nuclear 

reactors, linear accelerators, and radiography equipment. The source term and activity data available 

to NIOSH are inadequate to supplement the dose reconstruction process for the performance of 

sufficiently-accurate dose reconstructions for the BNL class under evaluation in the absence of 

personnel or workplace monitoring data.

Additional information regarding the BNL source term data available to NIOSH can be found in the 

related evaluation report for BNL petition SEC-00113 (NIOSH, 2009), and the BNL Technical Basis 

Document (ORAUT-TKBS-0048).

6.0 Feasibility of Dose Reconstruction for the Proposed Class

42 C.F.R. § 83.14(b) states that HHS will consider a NIOSH determination that there was insufficient 

information to complete a dose reconstruction, as indicated in this present case, to be sufficient,

without further consideration, to conclude that it is not feasible to estimate the levels of radiation 

doses of individual members of the class with sufficient accuracy. 

In the case of a petition submitted to NIOSH under 42 C.F.R. § 83.9(b), NIOSH has already 

determined that a dose reconstruction cannot be completed for an employee at the DOE or AWE 

facility. This determination by NIOSH provides the basis for the petition by the affected claimant. 

Per § 83.14(a), the NIOSH-proposed class defines those employees who, based on completed 

research, are similarly affected and for whom, as a class, dose reconstruction is similarly not feasible.

In accordance with § 83.14(a), NIOSH may establish a second class of co-workers at the facility for 

whom NIOSH believes that dose reconstruction is similarly infeasible, but for whom additional 

research and analysis is required. If so identified, NIOSH would address this second class in a 

separate SEC evaluation rather than delay consideration of the claim currently under evaluation (see 

Section 10). This would allow NIOSH, the Board, and HHS to complete, without delay, their 

consideration of the class that includes a claimant for whom NIOSH has already determined a dose 

reconstruction cannot be completed, and whose only possible remedy under EEOICPA is the addition 

of a class of employees to the SEC.
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This section of the report summarizes research findings by which NIOSH determined that it lacked 

sufficient information to complete the relevant dose reconstruction and on which basis it has defined 

the class of employees for which dose reconstruction is not feasible. NIOSH’s determination relies on 

the same statutory and regulatory criteria that govern consideration of all SEC petitions. 

6.1 Feasibility of Estimating Internal Exposures

NIOSH has evaluated the available personnel and workplace monitoring data and source term 

information and has determined that there are insufficient data for estimating internal exposures, as 

described below.

Despite the existence of organized occupational monitoring departments at BNL, some aspects of the 

personnel monitoring programs have been decentralized for much of the site’s history. This 

decentralization is particularly applicable to internal exposure monitoring record maintenance. 

Monitoring requirements were determined primarily within specific departments or divisions (e.g., 

Reactor Division) based on work area and specific activity. These requirements were accomplished 

via assignment of health physicists to specific BNL work areas. The health physicists determined

worker monitoring requirements under their purview based on their judgment of exposure potential. 

After analysis, personal monitoring results were returned to the area health physicists for comparison 

to standards in existence at the time, for assessment of safety adequacy, and for guidance for future 

monitoring. Internal monitoring results were frequently stored only in files located at the various site 

work areas. Records have also been stored in individual workers’ files, medical files, or vendor files 

that, in turn, may exist in several different locations on site or in off-site archives.

These personnel data management practices (i.e., lack of centralized databases) preclude the 

summarization and presentation of total internal monitoring data availability because of the inability 

of the site to efficiently or effectively retrieve and produce the data. In addition to complicating the 

data availability assessment, BNL’s data management practices have significantly affected the 

ultimate retrievability of internal monitoring data for the period prior to 1993 (based on the NIOSH 

efforts documented in this report). Retrievability issues were also a prevalent subject discussed in the 

previous site evaluation report for petition SEC-00113 (NIOSH, 2009). Data collected by NIOSH 

during an independent data capture was not included in record sets provided by BNL in response to 

requests for the monitoring records of specified former workers. In addition, an internal assessment 

aimed at evaluating BNL’s compliance with the guidance given in the DOE RadCon Manual 

recognized the difficulties created by the decentralized records and pointed to them as a factor in 

designating BNL as being in only partial compliance with the radiological records directives given in 

the DOE RadCon Manual (Review, 1992). 

Although an internal monitoring program was active throughout the period under evaluation, the 

program was not formally documented (Implementation Plan, 1991). As discussed earlier in this 

report, NIOSH has identified an internal monitoring procedure drafted by BNL in August 1993. Per 

the DOE RadCon Manual, this procedure required internal monitoring for any employee who had the 

potential to receive an annual internal exposure of 100 mrem or greater. The BNL internal monitoring 

procedure further specified which types of workers could be expected to receive such an exposure 

based on the nature of their job duties (Reciniello, 1993). 
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It is noteworthy that external radiation monitoring and the associated records have historically been 

more centralized. This may be due in part to the relatively low internal exposure potential for most 

work performed at BNL. From the beginning, an entity known as the “Personal Monitoring Group” 

collected and compiled all site external monitoring data for inclusion into external exposure summary 

reports, as required by the AEC/DOE. 

Consolidation of BNL monitoring records is an ongoing effort at BNL. Data storage technology, of 

course, has greatly improved since the first data were collected in 1947. Of note is the fact that, as 

early as 1990, a DOE Tiger Team Assessment of the BNL Radiation Protection Program remarked 

that “the external and internal dosimetry programs are adequate to assess workers’ radiation 

exposures... Internal radiation exposures are adequately assessed by use of whole body counters, 

thyroid counters, and urine analyses” (Tiger Team, 1990). An assessment performed by the DOE 

Chicago Operations Office in December 1993 found the BNL HP program “in compliance with 

applicable DOE standards and acceptable professional practices.” This assessment detailed the level 

of compliance for the external dosimetry program, the internal dosimetry program, the radiation and 

contamination survey program, and the personnel radiological records program (HP Assessment, 

1993). 

Some later assessments have been critical of some aspects of the BNL Radiological Protection 

Program (Assessment, 1999). However, the majority of these criticisms point to isolated incidences 

of noncompliance rather than evidence of a systemic problem with the program. Findings directed at 

documentation issues within the program admit that procedures exist and had been implemented for 

individual aspects of the internal dosimetry program, but the evaluators listed as a concern the absence 

of a single, overarching procedure to link the independent segments together. The only finding in 

regards to recordkeeping listed as a result of this assessment was the inability of a clerk to locate prior 

revisions of the internal dosimetry procedures (Assessment, 1999). Other findings, such as shortfalls 

in procedures for reporting doses to individuals or the lack of cohesiveness between BNL procedures 

and technical basis documents do not have an effect on NIOSH’s ability to reconstruct doses for 

individuals. 

The launch of the Health Physics Record System (HPRS) can be considered the most significant 

technology change to the program thus far. The HPRS was launched in 1996 with a phased 

implementation between March 1995 and January 1996. Prior to that time, data were kept on hard 

copy or in vendor files. 

Although documentation suggests that an internal monitoring program was active and documented 

during the period under evaluation, personnel data management practices (i.e., lack of centralized 

databases) preclude the summarization and presentation of total internal monitoring data availability. 

Based on data retrievability issues for personal internal monitoring data, NIOSH has concluded that it 

does not have access to sufficient personnel monitoring, workplace monitoring, or source term data to 

estimate potential internal exposures to various radionuclides during the period of DOE operations

evaluated in this report (i.e., 1980 through 1993 - 1993 marking the procedural implementation of a 

revised internal monitoring program). Consequently, NIOSH finds that it is not feasible to estimate, 

with sufficient accuracy, internal exposures to various radionuclides and resulting doses for the class 

of employees covered by this evaluation.
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Although NIOSH found that it is not possible to completely reconstruct internal radiation doses for the 

period from January 1, 1980 through December 31, 1993, NIOSH intends to use any internal 

monitoring data that may become available for an individual claim (and that can be interpreted using 

existing NIOSH dose reconstruction processes or procedures). Partial dose reconstructions for 

individuals employed in any area at Brookhaven National Laboratory during the period from January 

1, 1980 through December 31, 1993, but who do not qualify for inclusion in the SEC, may be 

performed using these data as appropriate.

6.2 Feasibility of Estimating External Exposures

This evaluation responds to a petition based on NIOSH determining that internal radiation exposures

to various radionuclides could not be reconstructed for a dose reconstruction referred to NIOSH by the 

Department of Labor (DOL). As noted above, HHS will consider this determination to be sufficient 

without further consideration to determine that it is not feasible to estimate the levels of radiation 

doses of individual members of the class with sufficient accuracy. Consequently, it is not necessary 

for NIOSH to fully evaluate the feasibility of reconstructing external radiation exposures for the class 

of workers covered by this report.

However, NIOSH has determined that, based on the available information, there is nothing that 

currently disputes its ability to reconstruct external exposures, including occupational medical doses, 

for all employees between January 1, 1980 and December 31, 1993, which is consistent with the 

determination in the evaluation of SEC-00113 (NIOSH, 2009).

6.3 Class Parameters Associated with Infeasibility

Some aspects of the personnel monitoring programs have been decentralized for much of the site’s 

history. This decentralization is particularly applicable to internal exposure monitoring record 

maintenance. Monitoring requirements were determined primarily within specific departments or 

divisions (e.g., Reactor Division) based on work area and specific activity. 

These personnel data management practices (i.e., lack of centralized databases) preclude the

summarization and presentation of total internal monitoring data availability. In addition to 

complicating the data availability assessment, BNL’s data management practices have apparently 

adversely affected the ultimate retrievability of internal monitoring data collected prior to 1993. 

Retrievability issues became evident as a result of a previous site evaluation. Data collected by 

NIOSH during an independent data capture was not included in record sets provided by BNL in 

response to requests for the monitoring records of specified former workers. 

An assessment performed by the DOE Chicago Operations Office in December 1993 found the BNL 

HP program “in compliance with applicable DOE standards and acceptable professional practices.” 

This assessment detailed the level of compliance for the external dosimetry program, the internal 

dosimetry program, the radiation and contamination survey program, and the personnel radiological 

records program (HP Assessment, 1993). NIOSH therefore recommends that the class include the 

time period from January 1, 1980 through December 31, 1993. 
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Although the High Flux Beam Reactor, Medical Research Reactor, Alternating Gradient Synchrotron, 

Brookhaven Linac Isotopes Production Facility, Chemistry Linac Irradiation Facility, Van de Graaf 

facilities, and National Synchrotron Light Source are specifically identified for the use of AEC-related 

radiological materials, documentation available to NIOSH does not indicate any definite boundaries 

between radiological and non-radiological areas for the period being evaluated. NIOSH recommends 

that the proposed worker class definition include ALL buildings and locations during the specified 

time period.

Although the BNL Personnel Monitoring Policy was to provide a radiation dosimeter to all workers 

who had the potential to receive external exposure, NIOSH has determined that the site-specific and 

claimant-specific data available for BNL for the time period under evaluation are insufficient to allow 

NIOSH to determine that any specific work group was not potentially exposed to radioactive material 

releases or possible subsequent contamination. NIOSH has insufficient information associating job 

titles and/or job assignments with specific radiological operations or conditions. Without such 

information, NIOSH is unable to define potential radiation exposure conditions based on worker job 

descriptions. NIOSH therefore recommends that the proposed worker class definition include all

workers at BNL during the specified time period. 

7.0 Summary of Feasibility Findings for Petition SEC-00196

This report evaluates the feasibility for completing dose reconstructions for employees at Brookhaven 

National Laboratory from January 1, 1980 through December 31, 1993. NIOSH determined that 

members of this class may have received radiation exposures from both internal and external sources 

of radiation. NIOSH lacks sufficient information, which includes in vivo and in vitro monitoring data

that would allow it to estimate the potential internal exposures to which the proposed class may have 

been exposed.

NIOSH has documented herein that it cannot complete the dose reconstruction related to this petition. 

The basis of this finding demonstrates that NIOSH does not have access to sufficient information to 

estimate either the maximum radiation dose incurred by any member of the class or to estimate such 

radiation doses more precisely than a maximum dose estimate.

NIOSH has determined that sufficient information exists and is readily retrievable to allow for the 

reconstruction of external exposures, including occupational medical doses, for all employees between 

January 1, 1980 and December 31, 1993, consistent with the determination in the evaluation of SEC00113 (NIOSH, 2009).

Although NIOSH found that it is not possible to completely reconstruct radiation doses for the 

proposed class, NIOSH intends to use any internal and external monitoring data that may become 

available for an individual claim (and that can be interpreted using existing NIOSH dose 

reconstruction processes or procedures). Therefore, dose reconstructions for individuals employed in 

any area at Brookhaven National Laboratory during the period from January 1, 1980 through 

December 31, 1993, but who do not qualify for inclusion in the SEC, may be performed using these 

data as appropriate.
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8.0 Evaluation of Health Endangerment for Petition SEC-00196

The health endangerment determination for the class of employees covered by this evaluation report is 

governed by EEOICPA and 42 C.F.R. § 83.14(b) and § 83.13(c)(3). Pursuant to these requirements, if 

it is not feasible to estimate with sufficient accuracy radiation doses for members of the class, NIOSH 

must determine that there is a reasonable likelihood that such radiation doses may have endangered 

the health of members of the class. The regulations require NIOSH to assume that any duration of 

unprotected exposure may have endangered the health of members of a class when it has been 

established that the class may have been exposed to radiation during a discrete incident likely to have 

involved levels of exposure similarly high to those occurring during nuclear criticality incidents. If 

the occurrence of such an exceptionally high-level exposure has not been established, then NIOSH is

required to specify that health was endangered for those workers who were employed for a number of 

work days aggregating at least 250 work days within the parameters established for the class or in 

combination with work days within the parameters established for one or more other classes of 

employees in the SEC. 

NIOSH has determined that members of the class were not exposed to radiation during a discrete 

incident likely to have involved levels of exposure similarly high to those occurring during nuclear

criticality incidents. However, the evidence reviewed in this evaluation indicates that some workers in 

the class may have accumulated chronic radiation exposures through intakes of radionuclides and 

from direct exposure to radioactive materials. Consequently, NIOSH is specifying that health was 

endangered for those workers covered by this evaluation who were employed for a number of work 

days aggregating at least 250 work days within the parameters established for this class or in 

combination with work days within the parameters established for one or more other classes of 

employees in the SEC.

9.0 NIOSH-Proposed Class for Petition SEC-00196

The evaluation defines a single class of employees for which NIOSH cannot estimate radiation doses 

with sufficient accuracy. This class includes all employees of the Department of Energy, its 

predecessor agencies, and its contractors and subcontractors who worked in any area at Brookhaven 

National Laboratory in Upton, New York, from January 1, 1980 through December 31, 1993, for a 

number of work days aggregating at least 250 work days, occurring either solely under this 

employment, or in combination with work days within the parameters established for one or more 

other classes of employees in the Special Exposure Cohort.
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10.0 Evaluation of Second Similar Class

In accordance with § 83.14(a), NIOSH may establish a second class of co-workers at the facility, 

similar to the class defined in Section 9.0, for whom NIOSH believes that dose reconstruction may not 

be feasible, and for whom additional research and analyses is required. If a second class is identified, 

it would require additional research and analyses. Such a class would be addressed in a separate SEC 

evaluation rather than delay consideration of the current claim. At this time, NIOSH has not identified 

a second similar class of employees at the Brookhaven National Laboratory for whom dose 

reconstruction may not be feasible.
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11.0 References

42 C.F.R. pt. 81, Guidelines for Determining the Probability of Causation Under the Energy 

Employees Occupational Illness Compensation Program Act of 2000; Final Rule, Federal 

Register/Vol. 67, No. 85/Thursday, p 22,296; May 2, 2002; SRDB Ref ID: 19391

42 C.F.R. pt. 82, Methods for Radiation Dose Reconstruction Under the Energy Employees 

Occupational Illness Compensation Program Act of 2000; Final Rule; May 2, 2002; SRDB Ref ID: 

19392

42 C.F.R. pt. 83, Procedures for Designating Classes of Employees as Members of the Special 

Exposure Cohort Under the Energy Employees Occupational Illness Compensation Program Act of 

2000; Final Rule; May 28, 2004; SRDB Ref ID: 22001

42 U.S.C. §§ 7384-7385 [EEOICPA], Energy Employees Occupational Illness Compensation 

Program Act of 2000; as amended; DCAS website

AEC, 1963, Division of Inspection Report; United States Atomic Energy Commission (AEC); April 

11, 1963; SRDB Ref ID: 9714

AEC, 1970, 1970 Whole-Body Radiation Exposure Summaries, various sites; Atomic Energy 

Commission (AEC); 1970; SRDB Ref ID: 13801

AEC, 1972, 1972 Whole-Body Radiation Exposure Summaries, various sites; Atomic Energy 

Commission (AEC); 1972; SRDB Ref ID: 13802

AEC, 1973, 1973 Whole-Body Radiation Exposure Summaries, various sites; Atomic Energy 

Commission (AEC); 1973; SRDB Ref ID: 13803

Assessment, 1999, Assessment of Brookhaven National Laboratory’s Internal Dosimetry Program; 

U.S. Department of Energy, Brookhaven Group, Operations Management Division; March 1 – April 

8, 1999; SRDB Ref ID: 94034

BNL, 1947, Proposed Precautionary Measures Against Laboratory Contamination; Brookhaven 

National Laboratory (BNL); 1947; SRDB Ref ID: 50599

BNL, 1948; Procedures Covering the Handling of S/F Materials and S/F Accountability Records for 

Brookhaven National Laboratory; Brookhaven National Laboratory (BNL); November 3, 1948; 

SRDB Ref ID: 55674

BNL, October 1957, Nuclear Engineering Department LMFR Report for October 1957; Brookhaven 

National Laboratory (BNL) Nuclear Engineering Department; October 28, 1957; SRDB Ref ID: 

55443

BNL, December 1957, Nuclear Engineering Department Monthly Progress Letter for December 

1957; Brookhaven National Laboratory (BNL) Nuclear Engineering Department; December 26, 1957; 

SRDB Ref ID: 55439
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BNL, 1960-1966, Organization Charts for the Health Physics Division of Brookhaven National 

Laboratory; Brookhaven National Laboratory (BNL); June 1960-May 1966; SRDB Ref ID: 55654

BNL, 1990-1991a, Workplace Airborne Activity Correspondence and Results; Brookhaven National 

Laboratory (BNL); September 1990 through October 23, 1991; SRDB Ref ID: 50534

BNL, 1990-1991b, Workplace Radioactive Air Monitoring Correspondence and Results; Brookhaven 

National Laboratory (BNL); September 1990 through October 4, 1991; SRDB Ref ID: 50536

BNL, 1995, Radiological Control Manual, Chapter 5: Radiological Health Support Operations; 

Brookhaven National Laboratory; November 20, 1995; SRDB Ref ID: 22455

Bubble Chamber, 1973, Monthly Report – September 1973, memorandum to C. B. Meinhold from W. 

R. Casey; Brookhaven National Laboratory; October 10, 1973; SRDB Ref ID: 55414, pdf p. 12

Cowan, 1947, Alpha Contamination of the Graphite Lab, correspondence to Lyle Berst; F. P. Cowan; 

August 22, 1947; SRDB Ref ID: 55361

Cowan, 1948, Material for Six Month Progress Report of December 31, 1948, correspondence to J. B. 

H. Kuper; F. P. Cowan; December 27, 1948; SRDB Ref ID: 50610

DHHS, 2010, Final Effect of Designation of a Class of Employees for Addition to the Special 

Exposure Cohort – Brookhaven National Laboratory; Department of Health and Human Services

(DHHS); January 9, 2010; OSA Ref ID: 111128

DOE, 1996, Highly Enriched Uranium Working Group Report on Environmental, Safety, and Health 

(ES&H) Vulnerabilities Associated with the Department’s Storage of Highly Enriched Uranium, 

DOE/EH-0525; Department of Energy (DOE); September 1996; SRDB Ref ID: 22030

ERDA, 1977, Final Environmental Impact Statement for Brookhaven National Laboratory in Upton, 

New York, ERDA-1540 UC-2, 11; Energy Research & Development Administration (ERDA); July 

1977; SRDB Ref ID: 6384

Flood, 1967, Tritium Exposure at Medical, correspondence to L. Gemmell; C. Flood; April 4, 1967; 

SRDB Ref ID: 50933 pdf p. 3

Flood, 1972, Contaminated Oil at 3.5 MeV Van de Graaff, correspondence to J. Weneser; C. Flood; 

April 4, 1972; SRDB Ref ID: 53529

Flood, 1982, Radiation Safety Systems at Brookhaven National Laboratory’s Low-Energy 

Accelerators; Charles W. Flood, Jr., Safety & Environmental Protection Division of Brookhaven 

National Laboratory; 1982; SRDB Ref ID: 22488

Flores, 1998, Dispersible Radioactive Material Inventory, correspondence to Department Chairs; E. 

A. Flores; December 22, 1998; SRDB Ref ID: 53365
SEC-00196 1-05-12 BNL

43 of 58

Fox, 1950, Revised Manual on Procedures and Facilities for Handling S/F Materials, correspondence 

to Department Heads; M. Fox; May 8, 1950; SRDB Ref ID: 55665

Haworth, 1960, August 2, 1960 Alpha Contamination Incident, correspondence to E. L. Van Horn; 

Leland J. Haworth; September 29, 1960; SRDB Ref ID: 6271

Hayner, 1947, Polonium-Beryllium Source, correspondence to T. S. Chapman from J. H. Hayner; 

April 28, 1947; SRDB Ref ID: 6283, pdf p. 19

Holeman, 1999, Personnel Monitoring Training Plan; Procedure No. PM-QAP-002; Brookhaven 

National Laboratory Radiation Control Division; August 4, 1999; SRDB Ref ID: 56364

HP Assessment, 1993, Radiological Control Manual 1993 Implementation Status Report, Brookhaven 

National Laboratory Associated Universities, Inc.; December 17, 1993; SRDB Ref ID: 48473, pdf 

p. 3

HP Procedures, 1948, General Health Physics Procedures, memorandum from F.P. Cowan to 

Members Radiation Safety Committee; Brookhaven National Laboratory; February 18, 1948; SRDB 

Ref ID: 50635

HP Summary, March 1949, Health Physics and Safety Summary for March 1949; Brookhaven 

National Laboratory (BNL); March 1949; SRDB Ref ID: 55453, pdf p. 31

HP Summary, October 1949, Health Physics Summary for October 1949; Brookhaven National 

Laboratory (BNL); October 1949; SRDB Ref ID: 55453, pdf p. 7

HP Summary, February 1959, Health Physics and Safety Summary for February 1959; Brookhaven 

National Laboratory (BNL); February 1959; SRDB Ref ID: 55502, pdf p. 32

HP Summary, May 1959, Health Physics and Safety Summary for May 1959; Brookhaven National 

Laboratory (BNL); May 1959; SRDB Ref ID: 55502, pdf p. 22

HP Summary, January 1961, Health Physics and Safety Summary for January 1961; Brookhaven 

National Laboratory (BNL); January 1961; SRDB Ref ID: 55494, pdf p. 33

HP Summary, October 1964, Health Physics and Safety Summary for October 1964; Brookhaven 

National Laboratory (BNL); October 1964; SRDB Ref ID: 55601, pdf p. 10

HP Summary, April 1965, Health Physics and Safety Summary for April 1965; Brookhaven National 

Laboratory (BNL); April 1965; SRDB Ref ID: 55600, pdf p. 30

HP Summary, June 1965, Health Physics and Safety Summary for June 1965; Brookhaven National 

Laboratory (BNL); June 1965; SRDB Ref ID: 55600, pdf p. 24

HP Summary, January 1966, Health Physics and Safety Summary for January 1966; Brookhaven 

National Laboratory (BNL); January 1966; SRDB Ref ID: 55599, pdf p. 52
SEC-00196 1-05-12 BNL

44 of 58

HP Summary, March 1966, Health Physics and Safety Summary for March 1966; Brookhaven 

National Laboratory (BNL); March 1966; SRDB Ref ID: 55599, pdf p. 49

HP Summary, May 1966, Health Physics and Safety Summary for May 1966; Brookhaven National 

Laboratory (BNL); May 1966; SRDB Ref ID: 55599, pdf p. 37

HP Summary, April 1967, Health Physics and Safety Summary for April 1967; Brookhaven National 

Laboratory (BNL); April 1967; SRDB Ref ID: 55606, pdf p. 34

HP Summary, April 1969, Health Physics and Safety Summary for April 1969; Brookhaven National

Laboratory (BNL); April 1969; SRDB Ref ID: 55604, pdf p. 39

HP Summary, October 1969, Health Physics and Safety Summary for October 1969; Brookhaven 

National Laboratory (BNL); October 1969; SRDB Ref ID: 55604, pd p. 9

HP Summary, February 1970, Health Physics and Safety Summary for February 1970; Brookhaven 

National Laboratory (BNL); February 1970; SRDB Ref ID: 53907, pdf p. 39-42

HP Summary, June 1971, Health Physics and Safety Summary for June 1971; Brookhaven National 

Laboratory (BNL); June 1971; SRDB Ref ID: 55602, pdf p. 35

HP Summary, September 1971, Health Physics and Safety Summary for September 1971; Brookhaven 

National Laboratory (BNL); September 1971; SRDB Ref ID: 55602, pdf p. 17

HP Summary, October 1971, Health Physics and Safety Summary for October 1971; Brookhaven 

National Laboratory (BNL); October 1971; SRDB Ref ID: 55602, pp. 11

Hull, 1977, Assignment of [name redacted] to Oversee Whole Body Counting Program, 

correspondence to R. G. Love; A. P. Hull; December 1, 1977; SRDB Ref ID: 55246

Implementation Plan, 1991, BNL 5480.11 Implementation Plan Status, memorandum from W. R. 

Casey to H. F. Kahnhauser with attached matrix; Brookhaven National Laboratory; December 5, 

1991; SRDB Ref ID: 48472, pdf pp. 2-6

Lancaster, 1949, Request for Polonium-210, correspondence to E. B. Meservey from J. H. Lancaster; 

October 6, 1949; SRDB Ref ID: 45053, pdf p. 2

Lazo, 1988a, Air Samples and Airborne Activity for Percussion Welding Pins into Uranium Plates, 

correspondence to John Taylor; Ted Lazo; June 23, 1988; SRDB Ref ID: 50626

Lazo, 1988b, Urine Sample Bioassay Requirements at Building 1008, correspondence to N. Rohrig; T. 

Lazo; March 8, 1988; SRDB Ref ID: 50688

Lessard, 2009, Brookhaven National Laboratory Accelerator Facilities Building 912, draft; E. T. 

Lessard; February 18, 2009; SRDB Ref ID: 60143
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45 of 58

Liverman, 1977, Final Environmental Impact Statement: Brookhaven National Laboratory, Upton, 

New York; James L. Liverman, Energy Research & Development Administration; July 1977; SRDB 

Ref ID: 6384

Lukas, 1986, Annual Bioassay Program, correspondence to R. Miltenberger; A. E. Lukas; March 3, 

1986; SRDB Ref ID: 50619

Miltenberger, 1995, Technical Justification for Not Using Working Levels in Radiation Dose 

Assessments, correspondence to H. Kahnhauser; R. Miltenberger; February 15, 1995; SRDB Ref ID: 

48514

Musolino, 2000, Technical Basis for Bioassay Requirements for BGRR Decommissioning Project; 

Stephen V. Musolino; September 27, 2000; SRDB Ref ID: 22428, pdf pp. 2-9

NIOSH, 2009, SEC Petition Evaluation Report for Petition SEC-00113, Brookhaven National 

Laboratory; National Institute for Occupational Safety and Health (NIOSH); Septemeber 29, 2009; 

SRDB Ref ID: 79629

OCAS-IG-001, External Dose Reconstruction Implementation Guidelines, Rev.1, National Institute 

for Occupational Safety and Health; Office of Compensation Analysis and Support; 2002; SRDB Ref 

ID: 38864

ORAUT-TKBS-0048, Summary Site Profile Document for the Brookhaven National Laboratory, Rev. 

00; Oak Ridge Associated Universities; August 30, 2006; SRDB Ref ID: 30090

Personal Communication, 2008, Personal Communication with Health Physics Manager, Telephone 

Interview by ORAU Team; December 11, 2008; SRDB Ref ID: 65827

Personnel Monitoring, 1948, Proposed SPI on Personnel Monitoring, memorandum from F. P. Cowan 

to Policy and Program Committee; Brookhaven National Laboratory; January 21, 1948; SRDB Ref 

ID: 50636

Personnel Monitoring, unknown date, General Procedures for Personnel Monitoring; Brookhaven 

National Laboratory; unknown date; SRDB Ref ID: 50569

Pocket Chambers, 1952, Use of Pocket Ionization Chambers, memorandum from F. P. Cowan to 

Members of Radiation Safety Committee; Brookhaven National Laboratory; May 12, 1952; SRDB 

Ref ID: 50598, pdf p. 7

Progress Report, March 1952, Progress Report for March 1952; W. D. Small; March 31, 1952; SRDB 

Ref ID: 55243, pdf p. 18

Progress Report, April 1952, Progress Report for April 1952; W. D. Small; April 30, 1952; SRDB Ref 

ID: 55243, pdf p. 16

Progress Report, May 1952, Progress Report for May 1952; W. D. Small; June 2, 1952; SRDB Ref 

ID: 55243, pdf p. 14
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46 of 58

Progress Report, October 1952, Progress Report for October 1952; W. D. Small; November 3, 1952; 

SRDB Ref ID: 55243, pdf p. 5

Progress Report, November 1953, Progress Report, November 1953; L. Phillips; November 30, 1953; 

SRDB Ref ID: 55242, pdf p. 3

Progress Report, December 1953, Progress Report, December 1953; L. Phillips; January 4, 1954; 

SRDB Ref ID: 55242, pdf p. 2

Progress Report, June 1954, Progress Report, June 1954; L. Phillips; July 1, 1954; SRDB Ref ID: 

55241, pdf p. 10

Progress Report, August 1954, Progress Report, August 1954; L. Phillips; September 2, 1954; SRDB 

Ref ID: 55241, pdf p. 5

Progress Report, September 1963, Progress/Hot Lab Report for September 1963; C. Foelix and R. 

Stong; October 8 & 9, 1963; SRDB Ref ID: 53889, pdf p. 8

Progress Report, December 1963, Progress Reports for December 1963; R. Stong and C. Foelix; 

January 3 & 9, 1964; SRDB Ref ID: 53889, pdf p. 3

Progress Report, January 1965, Progress Reports/Hot Lab Reports for January 1965; C. Foelix, M. 

Hilgemeier, and R. W. Stong; February 2 & 8, 1965; SRDB Ref ID: 53871, pp. 24-26

Progress Report, April 1965, Progress Reports/Hot Lab Reports for April 1965; R. W. Stong, C. 

Foelix, and M. W. Hilgemeier; May 5, 7, and 17, 1965; SRDB Ref ID: 53871, pdf pp. 14-16

Progress Report, February 1967, Progress Report, February 1967, C. Foelix, R Stong, and A. Lukas; 

March 15, 1967; SRDB Ref ID: 53851, pdf p. 16

Progress Report, January 1974, Progress Report-Physics/Chemistry January, 1974; R. L. Gardner; 

February 15, 1974; SRDB Ref ID: 55322, pdf p. 22

Progress Report, September 1974, Progress Report-Physics/Chemistry June-July, 1974; R. L. 

Gardner; September 5, 1974; SRDB Ref ID: 55322, pdf p. 14

Progress Report, November 1975, Progress Report – November 1975, Physics/Chemistry, E. J. 

O’Connell, III; February 5, 1976; SRDB Ref ID: 55426

Progress Report, December 1975, Progress Report-Chemistry/Physics December, 1975; E. J. 

O’Connell III; March 2, 1976; SRDB Ref ID: 53926

Progress Report, Oct-Nov 1983, Progress Report for October/November 1983; E. N. Carter; 

December 15, 1983; SRDB Ref ID: 55042, pp. 2-5

Progress Reports, 1974, Progress Report for 1974; E. N. Carter; January-December 1974; SRDB Ref 

ID: 55336
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47 of 58

Reciniello, 1992, Respirator Use by RCG Personnel, correspondence to N. Holden; R. Reciniello; 

December 3, 1992; SRDB Ref ID: 48490

Reciniello, 1993, Internal Monitoring, Procedure RD APM 8.7; R. Reciniello; Brookhaven National 

Laboratory; August 13, 1993; SRDB Ref ID: 55393

Review, 1992, Review of Radiation Control Manual, Brookhaven National Laboratory; August 14, 

1992; SRDB Ref ID: 48474

Rice, 1966, Summaries of Fuels and Materials Development Programs, draft copy; edited by William 

L. R. Rice; March 1966; SRDB Ref ID: 21847

Safety Manual, 1948, Summary of Responsibilities in Regard to Radiation Safety, memorandum from 

F. P. Cowan to the Radiation Safety Committee Members; Brookhaven National Laboratory; March 1, 

1948; SRDB Ref ID: 50634

Salant, 1947, Precautions in Handling Radioactive Sources, correspondence to the Nuclear Interaction 

Group (P-32); E. Salant; November 18, 1947; SRDB Ref ID: 50602

Special Nuclear, 1963, Special Nuclear Material Draft, Brookhaven National Laboratory; April 4, 

1963; SRDB 45051, pdf p. 3

Tiger Team, 1990, Appendices, Tiger Team Assessment of the Brookhaven National Laboratory; U.S. 

Department of Energy, Environment, Safety and Health; DOE/EH—0140-Vol.2; June 1990; SRDB 

Ref ID: 48283

Urinalysis Records, 1952-1975a, BNL Urinalysis/Bioassay Records from September 5, 1952 through 

February 12, 1975; SRDB Ref ID: 48221

Urinalysis Records, 1952-1975b, BNL Urinalysis/Bioassay Records from May 28, 1952 through 

September 22, 1975; SRDB Ref ID: 48224

Use of Dosimetry, 1995, Use of Dosimetry, N. Contos; Brookhaven National Laboratory; FS-SOP4020; September 1, 1995; SRDB Ref ID: 50587

Van Horn, 1962-1963, Various Correspondence Regarding BNL Permits; B. L. Van Horn; June 11, 

1962 through May 9, 1963; SRDB Ref ID: 6517, pdf pp. 103-119

Volatility, 1957, Explosion at Brookhaven National Laboratory, office memorandum to K. E. Fields 

from M. Eisenbud; U.S. Atomic Energy Commission, New York Operations Office; June 7, 1957; 

SRDB Ref ID: 6319, pdf pp. 8-33

WBC Summary, 1960, Summary of Whole Body Radiation Exposures to External Penetrating 

Radiation Accumulated During the Year 1960, U.S. Atomic Energy Commission, New York 

Operations Office; 1960; SRDB Ref ID: 13786, pdf p. 44
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48 of 58

WBC Summary, 1961, Summary of Whole Body Radiation Exposures to External Penetrating 

Radiation Accumulated During the Year 1961, U.S. Atomic Energy Commission, New York 

Operations Office; 1961; SRDB Ref ID: 13789, pdf p. 47

WBC Summary, 1964, Summary of Whole Body Radiation Exposures to External Penetrating 

Radiation Accumulated During the Year 1964, U.S. Atomic Energy Commission, New York 

Operations Office; 1964; SRDB Ref ID: 14442, pdf p. 12

WBC Summaries, 1987, Various summaries of whole body count results for 1987, Brookhaven 

National Laboratory; various dates in 1987; SRDB Ref ID: 50416

Whole-Body Results, 1965-1969, 1965-1969 Exposure of AEC and AEC Contractor Personnel to 

Whole-Body Penetrating Radiation, various sites; Atomic Energy Commission (AEC); October 1965 

through December 31, 1969; SRDB Ref ID: 13800

Whole-Body Results, 1973-1981, BNL Whole-Body Counting Results from January 4, 1973 to 

December 12, 1981; SRDB Ref ID: 48265

Whole-Body Results, 1975-1981, BNL Whole-Body Counting Results from May 29, 1975 through 

November 20, 1981; SRDB Ref ID: 48247

Whole-Body Results, 1979-1986, BNL Whole-Body Counting Results from January 11, 1979 through 

October 23, 1986; SRDB Ref ID: 48248

Whole-Body Results, 1988-1994, BNL Whole-Body Counting Results from December 8, 1988 to July 

22, 1994; SRDB Ref ID: 50704

Whole-Body/Thyroid Results, 1983-1984, BNL Whole-Body and Thyroid Counting Results from 

November 22, 1983 to October 26, 1984; SRDB Ref ID: 48253
SEC-00196 1-05-12 BNL

Page 49 of 58

Attachment 1: Data Capture Synopsis

Table A1-1: Data Capture Synopsis for Brookhaven National Laboratory

Data Capture Information General Description of Documents Captured Date Completed Uploaded to 

SRDB

Primary Site/Company Name: Brookhaven National 

Laboratory DOE 1947-present

Other Company Names:

Associated Universities, Incorporated 

Brookhaven Science Associates 

Physical Site of the Site: 5320 Acres, 330 Buildings 

Site Population as of 10/2011:

2815 Employees

1500 Students

4354 Facility Users

Brookhaven histories and highlights, bioassay and whole body count 

reports, bioassay TBD for the Brookhaven Graphite Research Reactor 

(BGRR) decommissioning, High Flux Beam Reactor (HFBR) dose 

assessment reports, neutron dose distributions, Alternating Gradient 

Synchrotron (AGS) neutron dosimetry and surveys, internal dosimetry 

TBDs, medical x-ray QC report, incident reports, HFBR stack samples, 

the Radiation Control Manual, Health Physics summaries, HFBR whole 

body counts and bioassay results, dosimetry procedures, thyroid 

counting results, Tristan reports and dosimetry reports, individual 

employees' dosimetry results from their personnel monitoring and 

medical files, radiological and environmental surveys, facility progress 

and status reports, Marshall Islands reports, whole body counter 

logbooks, HFBR visitor registers, annual reports through 1970, 

accelerator radiation monitoring systems, decommissioning surveys and 

plans, a dosimetry database, and urinalysis results.

10/23/2011 2,910

State Contacted: NA Note: Contacting the state was not considered necessary since 

Brookhaven is an active DOE site and cooperated with relevant data 

collection.

09/11/2009 0

Curtiss-Wright A report from a radiological waste meeting hosted by Brookhaven. 03/10/2009 1

Department of Labor/Paragon Material transfer reports and reports on uranium oxide reduction. 12/30/2008 21

DOE Argonne National Laboratory - East A listing of Chicago Operations Office facilities, an ERDA neutron 

dosimetry conference, and 1961 weekly radiation safety summaries of 

Building 350. 

03/26/2008 3

DOE General Atomics Material transfer reports. 11/02/2005 1

DOE Germantown Reports on beryllium hazards and proposed standards, a DOL document 

acquisition request, Brookhaven EEOICPA search procedures, 

Brookhaven EEOICPA records chart spreadsheet, and Manhattan 

District history excerpts.

03/07/2011 7

DOE Hanford A 1967 Hanford report mentioning the potential sale of Co60 to 

Brookhaven, the December 1951 SF accountability report, and a 1952 

scrap recovery report.

07/28/2011 3
SEC-00196 1-05-12 BNL

50 of 58

Table A1-1: Data Capture Synopsis for Brookhaven National Laboratory

Data Capture Information General Description of Documents Captured Date Completed Uploaded to 

SRDB

DOE Idaho National Laboratory (INL)/SC&A Inventory and manufacturing statements and Chemical Processing Plant 

production monthly reports.

06/24/2010 46

DOE Lawrence Berkeley National Laboratory 

(LBNL)/SC&A

Safety problems and shielding of accelerators and treatment of 

radionuclide uptakes and intakes.

06/18/2009 3

DOE Lawrence Livermore National Laboratory (LLNL) An accelerator characterization report and a 1984 estimate of 

Brookhaven's person-rem tritium dose.

06/10/2009 2

DOE Legacy Management - Grand Junction Office Material transfer requests and reports, characterization of the BGRR 

canal, environmental reports, building survey and demolition reports, 

and operational reports.

08/25/2011 78

DOE Legacy Management - Morgantown Operational progress reports, a 1983 pollution standards report, a site 

summary of safety and health needs, and a 1993 occurrence report.

01/27/2011 6

DOE Legacy Management - MoundView (Fernald 

Holdings, includes Fernald Legal Database)

Waste management reports, air emissions reports, AEC reports to 

Congress, AEC bioassay and analytical chemistry conference, a report 

on the uptake and effects of thorium dioxide, and The 1953 Health and 

Safety Division annual report.

05/13/2010 16

DOE Los Alamos National Laboratory (LANL) Reports on mixed waste streams, AEC facilities information, 

photodosimetry, environmental impact statement - storage and 

disposition of weapons grade material.

12/06/2007 4

DOE Oak Ridge National Laboratory (ORNL) A report on the machining of uranium for the Brookhaven Graphite 

Research Reactor and a summary on the Kilrod Project.

04/12/2007 2

DOE Oak Ridge Operations Records Holding Task Group A 1955 site inspection,1947 film badge results, and transcripts of 1964 

interviews.

12/14/2010 18

DOE Office of Scientific and Technical Information 

(OSTI)

A 2002 site environmental report, a reactor progress report, Tiger Team 

action plan, pile operating manual, survey of irradiation facilities, 

human radiation experiments, and observations on chronic lymphocytic 

leukemia.

08/06/2009 13

DOE Pacific Northwest National Laboratories (PNNL) Results of the 1965 film badge reliability study. 12/29/2004 1

DOE Savannah River Site Savannah River Site dosimetry visitor cards from the 1950's. 08/26/2008 7

[Name redacted] A 1947 AEC recommendation for using vacations to recuperate from 

radiation exposure.

11/24/2009 1

[Name redacted] A 1983 PNL dosimetry performance comparison. 08/13/2003 1

Federal Records Center (FRC) - Denver A 1995 DOE occupational exposure report and the Photodosimetry 

Evaluation Book, Volume IV.

06/15/2010 2
SEC-00196 1-05-12 BNL

51 of 58

Table A1-1: Data Capture Synopsis for Brookhaven National Laboratory

Data Capture Information General Description of Documents Captured Date Completed Uploaded to 

SRDB

Federal Records Center (FRC) - Kansas City Film badge reports, individual employees' dosimetry information from 

their medical files, 1984-1985 High Flux Beam Reactor internal dose 

estimates, and exposure investigations.

07/01/2009 91

Federal Records Center (FRC) - San Bruno Associated Universities organizations and objectives, summaries of 

fuels and materials development programs, air sampling at reactor sites, 

and potential hazards of specific accelerators.

02/01/2006 4

Hagley Museum and Library Report of a 1951 health physics conference, reactor fuel reports, and 

Brookhaven's work with Hanford and Savannah River Site.

09/29/2010 7

Interlibrary Loan The Atoms for Peace Program, Brookhaven papers describing 

radiopharmaceuticals and defining low radiation doses, environmental 

levels of radioactivity at AEC installations, radiation dosimetry at 

Brookhaven reactors, and a history of the Brookhaven Graphite 

Reactor.

10/24/2011 20

Internet The 2003 DOE Occupational Radiation Exposure Report, accelerator 

physics, radiation dosimetry at Brookhaven reactors, and designation of 

a Brookhaven Special Exposure Cohort class.

3/9/2010 6

Internet - Comprehensive Epidemiologic Data Resource No relevant documents identified. 11/20/2011 0

Internet - Defense Technical Information Center (DTIC) The Brookhaven tritium leak, Alternating Gradient Synchrotron reports, 

application of the hot particle methodology to beta particle caused skin 

ulcers, and the 1949 safety manual.

10/3/2011 8

Internet - DOE A 1994 DOE handbook on airborne radioactivity releases from 

nonreactor facilities. 

12/4/2008 1

Internet - DOE Hanford Declassified Document Retrieval 

System (DDRS)

Monthly reports on Hanford/Brookhaven metallurgical projects, 

discussions of neutron monitoring and dosimetry, and nuclear reactor 

safety. These documents were added by site association review or 

previous data capture. 

10/13/2011 8

Internet - DOE Legacy Management Considered Sites No relevant documents identified. 10/13/2011 0

Internet - DOE National Nuclear Security Administration 

Library

No relevant documents identified. 10/13/2011 0

Internet - DOE OpenNet New York Operations Office (NYOO) status reports, AEC reports to 

Congress, human experimentation fact sheet, a summary history of the 

nuclear weapons program. These documents were added by site 

association review or previous data capture. 

10/14/2011 18

Internet - DOE OSTI Report on the fabrication of U-233 fuel rods. 03/18/2009 1
SEC-00196 1-05-12 BNL

52 of 58

Table A1-1: Data Capture Synopsis for Brookhaven National Laboratory

Data Capture Information General Description of Documents Captured Date Completed Uploaded to 

SRDB

Internet - DOE OSTI Energy Citations Brookhaven Highlights 1978-1994, appendices to the Tiger Team 

Assessment, metal hydride reports, institutional plans, reactor 

operations reports, and a 1972 Health Physics and Safety report.

10/16/2011 29

Internet - DOE OSTI Information Bridge Stannard's Radioactivity and Health, U-232 content of sapphire 

material, waste reports, human radiation experiments, radioisotope 

customers, environmental reports and plans, treatment planning at the 

Medical Research Reactor, High Flux Beam Reactor reports, 

Alternating Gradient Synchrtron shielding reports, and reactor 

operations reports.

10/23/2011 95

Internet - Google Histories of the reactors, environmental reports, reports to Congress, 

DOE occupational exposure reports, waste disposal reports, work force 

restructuring, environmental cleanup reports site history and 

description, soil cleanup reports, reactor decommissioning reports, and 

monthly progress reports.

10/23/2011 221

Internet - Health Physics Journal Articles on using a whole body counter to measure body burdens of a 

fallout-exposed population, an improved TLD system, radiation 

detection and alarm system for an accelerator complex, and the design 

and dosimetry of a strontium-yttrium beta irradiator. Searches to 

continue.

OPEN 4

Internet - Journal of Occupational and Environmental 

Hygiene

A 1961 article on design features and procedures for the new BNL 

laundry and decontamination facility, to be ordered.

OPEN 0

Internet - National Academies Press (NAP) No relevant documents identified. 10/13/2011 0

Internet - NRC ADAMS U.S. spent fuel and waste inventories reports, environmental reports, 

and an NRC assessment of the High Flux Beam Reactor.

8/26/2011 23

Internet- ORNL Library Fuel element report, isotope production reports, operations division 

reports, and waste disposal reports.

11/8/2011 11

Internet - USACE/FUSRAP No relevant documents identified. 10/13/2011 0

Internet - US Transuranium and Uranium Registries No relevant documents identified. 10/13/2011 0

Missouri Department of Natural Resources Report and appendix on environmental vulnerabilities of plutonium 

storage.

10/1/2008 2

Mound Museum References to Brookhaven in Mound employee newsletter. 5/18/2010 2

National Archives and Records Administration (NARA) -

Atlanta

DOE indoor radon study results, contamination of a Brookhaven 

zetraton neutron generator, polonium requests and requirements, U-233 

reports, 1989 shipments, directory of AEC consultants, a report of a 

visit to Harshaw Chemical Company, hospitalization of a Harshaw 

employee at Brookhaven for a kidney study.

05/23/2008 13
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53 of 58

Table A1-1: Data Capture Synopsis for Brookhaven National Laboratory

Data Capture Information General Description of Documents Captured Date Completed Uploaded to 

SRDB

National Archives and Records Administration (NARA) -

College Park

Waste reports, weekly and monthly status reports, NIOSH/ORAU Team 

researcher notes, uranium rod fabrication and shipping, industrial health 

advisory board report, and thorium research planning report.

07/16/2010 21

National Institute for Occupational Safety and Health 

(NIOSH)

Worker outreach meeting minutes. 12/01/2009 26

National Institute for Occupational Safety and Health 

(NIOSH)/SC&A

Highly enriched uranium working group reports. 02/16/2006 4

New South Associates History of Savannah River Site with references to Brookhaven. 08/18/2009 1

Nuclear Regulatory Commission Public Document Room Research activities progress reports and chemical changes in high level 

waste after 1000 years.

09/01/2011 2

Oak Ridge Library for Dose Reconstruction A metal recovery report, waste reports, a 1957 isotopes division report, 

and history of ORNL.

5/12/2011 8

Oak Ridge Reading Room A 1949 SF material accountability report. 04/08/2011 1

Ohio Department of Health Chicago Operations Office environmental restoration and waste 

management site-specific plans.

11/3/2008 1

ORAU Team Summary site profile, process knowledge expert interviews, and 

reviews of potential environmental release points.

07/28/2011 270

R.S. Landauer Radiation dosimetry reports. 4/20/2010 214

S. Cohen & Associates (SC&A) Process knowledge expert interviews, AEC neutron dosimetry 

workshop, Building 801 reports, neutron foil dosimetry of the BLIP 

facility, accelerator produced radionuclides, and the Safety and 

Environmental Protection Division file index. 

08/14/2009 34

Science Applications International Corp (SAIC) Radiation exposure summaries. 09/02/2004 9

Southern Illinois University, Edwardsville, IL Disposal of Brookhaven wastes in the St. Louis area, AEC construction 

cost differentials, nuclear fuels development report, and the AEC 

cryptographic telephone network.

10/21/2008 4

University of Colorado Norlin Library AEC and ERDA workshops on personnel neutron dosimetry and costs 

and benefits of a formal safety program.

04/10/2006 3

University of Rochester Miner Library Using threshold detectors for neutron measurement at the Cosmotron. 08/21/2009 1

University of Tennessee Hodges Library 1948 and 1949 Health Physics summaries and a dosimetry report from 

ORNL to Brookhaven.

10/11/2011 3

Unknown Site and NYOO status reports, environmental reports, and beryllium 

reports.

04/25/2005 91
SEC-00196 1-05-12 BNL

54 of 58

Table A1-1: Data Capture Synopsis for Brookhaven National Laboratory

Data Capture Information General Description of Documents Captured Date Completed Uploaded to 

SRDB

Viacom Records A newsletter noting that Westinghouse equipment powered the 

Brookhaven Cosmotron.

12/06/2004 1

TOTAL 4,404

Table A1-2: Databases Searched for Brookhaven National Laboratory

Database/Source Keywords / Phrases Hits Selected

NOTE: Database search terms employed for each of the databases listed below are available 

in the Excel file called “Brookhaven National Laboratory Rev 01, (83.14) 11-22-11”

DOE CEDR

http://cedr.lbl.gov/

COMPLETED 11/20/2011

See Note above 1 0

DOE Hanford DDRS

http://www2.hanford.gov/declass/

COMPLETED 10/13/2011

See Note above 17 0

DOE Legacy Management Considered Sites

http://csd.lm.doe.gov/

COMPLETED 10/13/2011

See Note above 161 0

DOE NNSA - Nevada Site Office

www.nv.doe.gov/main/search.htm

COMPLETED 10/13/2011

See Note above 0 0

DOE OpenNet

http://www.osti.gov/opennet/advancedsearch.jsp

COMPLETED 10/14/2011

See Note above 3,518 0

DOE OSTI Energy Citations

http://www.osti.gov/energycitations/

COMPLETED 10/16/2011

See Note above 84,878 29

DOE OSTI Information Bridge

http://www.osti.gov/bridge/advancedsearch.jsp

COMPLETED 10/23/2011

See Note above 44,800 95
SEC-00196 1-05-12 BNL

55 of 58

Table A1-2: Databases Searched for Brookhaven National Laboratory

Database/Source Keywords / Phrases Hits Selected

Google

http://www.google.com

COMPLETED 10/23/2011

See Note above 192,734,834 221

Journal of Occupational and Environmental Health 

http://www.ijoeh.com/index.php/ijoeh

COMPLETED 11/20/2011

See Note above 1 0

National Academies Press

http://www.nap.edu/

COMPLETED 10/13/2011

See Note above 24,719 0

NRC ADAMS Reading Room

http://www.nrc.gov/reading-rm/adams/web-based.html

COMPLETED 04/14/2011

See Note above 4,238 16

USACE/FUSRAP

http://www.lrb.usace.army.mil/fusrap/

COMPLETED 10/13/2011

See Note above 0 0

U.S. Transuranium & Uranium Registries 

http://www.ustur.wsu.edu/

COMPLETED 10/13/2011

See Note above 7 0

Table A1-3: OSTI Documents Requested for Brookhaven National Laboratory

Document Number Document Title Requested

Date

Received

Date

BNL-7581; CONF-337-3

OSTI ID: 4129174

Monitoring the Cooling Air Effluent from the Brookhaven Graphite 

Research Reactor at the Point of Release and in the Environment dated 

November 1963

10/18/2011

BNL-736; BNL-T-265

OSTI ID: 4749855

Uranium-Bismuth In-Pile Corrosion Test Loop Radiation Loop No. 1 

dated May 1961

10/18/2011

BNL-12169

OSTI ID: 4555340

Evaluation of Fission Product and Activation Isotopes in a Reactor 

Stack Effluent and in the Nearby Environment dated October 31, 1968

10/18/2011

BNL-3146

OSTI ID: 4348577

Summary Hazards Report on Enriched Fuel Element Loading for the 

BNL Research Reactor dated May 24, 1956

10/18/2011

DOE/US-0017

OSTI ID: 6456599

Department of Energy's High Flux Beam Reactor (HFBR), September

15-19, 1980: An independent on-site safety review dated February 1981

10/18/2011
SEC-00196 1-05-12 BNL

56 of 58

Table A1-3: OSTI Documents Requested for Brookhaven National Laboratory

Document Number Document Title Requested

Date

Received

Date

TID-14771

OSTI ID: 4818160

Preliminary Hazards Summary Report on the Brookhaven High Flux 

Beam Research Reactor dated May 1961

10/18/2011

BNL-149

OSTI ID: 4390989

Quarterly Progress Report for October 1-December 31, 1951 

Unclassified Section dated March 1952

10/12/2011

BNL-189

OSTI ID: 4400080

Quarterly Progress Report for April 1-June 30, 1952 Unclassified 

Section dated October 1952

10/12/2011

BNL-93

OSTI ID: 4424416

Quarterly Progress Report for October 1-December 31, 1950 dated 

March 1951

10/12/2011

WHC-SP-0632

OSTI ID: 720991

Radioisotope production technology development; Annual report for 

fiscal year 1990

10/12/2011

BNL-50780

OSTI ID: 5044188

Ref ID: 83793

Tritium storage development. Progress report No. 14, OctoberDecember 1977. [As a tritide in a metal hydride]07/21/2010 07/29/2010

BNL-38317

OSTI ID: 5470215

Ref ID: 83795

Heat-actuated metal hydride hydrogen compressor testing 07/21/2010 07/29/2010

BNL-26047; CONF-790301-10

OSTI ID: 6051964

Ref ID: 83797

Metal hydride technology 07/21/2010 07/29/2010

BNL-25215; CONF-781142-2

OSTI ID: 6440486

Ref ID: 83799

Metal hydride research and development program at Brookhaven 

National Laboratory

07/21/2010 07/29/2010

BNL-22062; CONF-761134-2

OSTI ID: 7307323

Ref ID: 83800

Metal hydride materials program at BNL: current status and future plans 07/21/2010 07/29/2010

NA

OSTI ID: 441060

Ref ID: 71851

Design and Dosimetry of a Strontium-90--yttrium-90 Beta Irradiation 

Facility from Health Phys., v. 26, no. 1, pp. 99-101

07/21/2009 08/25/2009

CONF-8705273-

OSTI ID: 5168103

Ref ID: 71828

What is a Low Dose of Radiation from Int J Radiat Biol Relat Stud 

Phys, Chem, Med Vol. 53(1):1-12, 01/02/1988

07/21/2009 08/18/2009

NA

OSTI ID: 4096108

Ref ID: 71827

Radiopharmaceuticals from Phys. Rep., v. 21, no. 6, pp. 315-367 07/21/2009 08/18/2009

BNL-22664

OSTI ID: 6621747

Ref ID: 71825

Chronic Lymphocytic Leukemia: Concepts and Observations from 

Blood Cells Vol 3:637-649

07/21/2009 08/06/2009
SEC-00196 1-05-12 BNL

57 of 58

Table A1-3: OSTI Documents Requested for Brookhaven National Laboratory

Document Number Document Title Requested

Date

Received

Date

BNL-10490

OSTI ID: 4421770

Ref ID: 71849

Improved Thermoluminescence Dosimetry System from Health Phys., 

13: 567-73(June 1967).

07/21/2009 08/06/2009

BNL-17025

OSTI ID: 4569426

Ref ID: 71850

Radiation and Alarm System (Amos II) for Habitable Areas of an 

Accelerator Complex from Health Phys. 24: No. 4, 442-443(Apr 1973)

07/21/2009 08/06/2009

NA

OSTI ID: NA 

Ref ID: 56600

A Whole Body Counter with an Invariant Response to Radionuclide 

Distribution and Body Size by S. H. Cohn, et al., Phys. Med. Biol. 14:4, 

pp. 645-658 (1969)

12/22/2008 12/29/2008 -

Dr. Falco 

Provided

HKF-116(Rev)

OSTI ID: NA

Ref ID: 54015

Quarterly Report for October 1 to December 31, 1951 10/19/2007 11/04/2008

HKF-1492D-41(Del)

OSTI ID: NA

Ref ID: 54017

Plutonium Production Reactor Progress Memorandum dated 9/25/1951 10/19/2007 11/04/2008

M-4414

OSTI ID: NA

Red ID: 54018

Brookhaven National Laboratory Pile Operating Manual Book No. 2 

dated 4/1/1949

10/19/2007 11/04/2008

HKF-1492D-39

OSTI ID: NA

Ref ID: 53179

Criticality Hazards in Processing 1% Enriched Uranium dated 

9/24/1951

10/19/2007 11/03/2008

BNL-52256

OSTI ID: 6628605

Ref ID: 48682

Action Plan for the Tiger Team Assessment Report dated 8/30/1990 08/07/2008 09/18/2008

DOE/EH-0140 Vol. 2

OSTI ID: 6774838

Ref ID: 48283

Tiger Team Assessment of the Brookhaven National Laboratory 

Volume 2 dated 06/01/1990 

08/07/2008 08/28/2008
SEC-00196 1-05-12 BNL

58 of 58

Table A1-4: Interlibrary Loan Documents Requested for Brookhaven National Laboratory

Document Number Document Title Requested

Date

Received

Date

OSTI ID: 4709767

Ref ID: 102604

12 Years Experience Operating the Brookhaven Graphite Reactor from 

Nucleonics Volume 21 pages 2, 60 dated February 1963

10/18/2011 10/24/2011

OSTI ID: 20005835

Ref ID: 102603

Radiation Dosimetry at the BNL Reactor Facilities from Transactions of 

the American Nuclear Society, Journal Volume 81, Conference: 

American Nuclear Society 1999 Winter Meeting, 11/14/1999-

11/18/1999

10/18/2011 10/24/2011

Table A1-5: DTIC Documents Requested for Brookhaven National Laboratory

Document Number Document Title Requested

Date

Received

Date

BNL/NPB-88-33 200-MeV Neutral Beam Test Facility Description and Radiation Safety 11/14/2011